Effects of Boiling Water Reactor Medium on the Fatigue Life of Austenitic Stainless Steels
Author:
Affiliation:
1. Primary Components and Calculations, AREVA GmbH, Henri-Dunant Street 50, Erlangen 91058, Germany e-mail:
2. Department of Mechanical Engineering, University of Erlangen-Nuremberg, Egerland Street 5, Erlangen 91058, Germany e-mail:
Abstract
Publisher
ASME International
Subject
Mechanical Engineering,Mechanics of Materials,Safety, Risk, Reliability and Quality
Link
http://asmedigitalcollection.asme.org/pressurevesseltech/article-pdf/doi/10.1115/1.4032651/6317347/pvt_138_03_031406.pdf
Reference39 articles.
1. Effect of LWR Coolant Environments on the Fatigue Life of Reactor Materials,2014
2. Nuclear Power Generation Facilities—Environmental Fatigue Evaluation Method for Nuclear Power Plants,2011
3. Statistical Models of Mean Stress and Water Environment Effects on the Fatigue Behavior of 304 Stainless Steel,1997
4. Prediction Model for Corrosion Fatigue Lives of Austenitic Stainless Steels in Pressurized Water Reactor Environments;Corrosion,2012
5. Effects of Pressurized Water Reactor Medium on the Fatigue Life of Austenitic Stainless Steels;ASME J. Pressure Vessel Technol.,2015
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