Effects of pressurized water reactor medium on the fatigue life of austenitic stainless steels

Wilhelm, P., Rudolph, J. and Steinmann, P. (2015) Effects of pressurized water reactor medium on the fatigue life of austenitic stainless steels. Journal of Pressure Vessel Technology, 137(6), 061404. (doi: 10.1115/1.4029832)

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Abstract

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.

Item Type:Articles
Status:Published
Refereed:Yes
Glasgow Author(s) Enlighten ID:Steinmann, Professor Paul
Authors: Wilhelm, P., Rudolph, J., and Steinmann, P.
College/School:College of Science and Engineering > School of Engineering > Infrastructure and Environment
Journal Name:Journal of Pressure Vessel Technology
Publisher:American Society of Mechanical Engineers
ISSN:0094-9930
ISSN (Online):1528-8978
Published Online:01 December 2015
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