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Research Papers: Materials and Fabrication

Effects of Pressurized Water Reactor Medium on the Fatigue Life of Austenitic Stainless Steels

[+] Author and Article Information
Paul Wilhelm

Mechanical Analyses,
AREVA GmbH,
Henri-Dunant-Str. 50,
Erlangen 91058, Germany
e-mail: paul.wilhelm@areva.com

Jürgen Rudolph

Mechanical Analyses,
AREVA GmbH,
Henri-Dunant-Str. 50,
Erlangen 91058, Germany
e-mail: rudolph.juergen@areva.com

Paul Steinmann

Department of Mechanical Engineering,
University of Erlangen–Nuremberg,
Egerlandstr. 5,
Erlangen 91058, Germany
e-mail: paul.steinmann@ltm.uni-erlangen.de

If documented.

If documented.

Contributed by the Pressure Vessel and Piping Division of ASME for publication in the JOURNAL OF PRESSURE VESSEL TECHNOLOGY. Manuscript received November 28, 2014; final manuscript received February 11, 2015; published online May 21, 2015. Assoc. Editor: Marina Ruggles-Wrenn.

J. Pressure Vessel Technol 137(6), 061404 (Dec 01, 2015) (7 pages) Paper No: PVT-14-1194; doi: 10.1115/1.4029832 History: Received November 28, 2014; Revised February 11, 2015; Online May 21, 2015

A statistical model for austenitic stainless steels for predicting the effect of pressurized water reactor (PWR) environments on fatigue life for a range of temperatures and strain rates is developed based on analysis of available material data from USA, Europe, and Japan. Only fatigue data from polished specimens of wrought material tested under strain control were considered. Hollow specimens were not treated in the final calculations. The fatigue life correction factors were defined as the ratio of life in water at 300 °C (572 °F) (reference conditions) to that in water at service conditions. The model is recommended for predicting fatigue lives that are 103–105 cycles.

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References

Figures

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Fig. 1

Best-fit curve in air at room temperature

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Fig. 10

Experimental and predicted values of fatigue lives

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Fig. 9

Fatigue life of type 304

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Fig. 8

Fatigue life of types 304 and 316NG at different tensile strain rates

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Fig. 7

Fatigue life of types 304L, 304, and 316NG

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Fig. 6

Strain rate correction factor

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Fig. 5

Effect of strain rate

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Fig. 4

Dependence of tensile strain rate on fatigue life

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Fig. 3

Fatigue life of type 304L in air and water environment

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Fig. 2

Reference curve for PWR medium environment

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Fig. 11

Experimental and predicted values of fatigue lives

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Fig. 12

Comparison of prediction models: effects of tensile strain rate

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Fig. 13

Comparison of prediction models for tube specimens

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