The effect of fast neutron irradiation upon the fatigue-crack propagation behavior of two austenitic stainless steels
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference27 articles.
1. Estimation of Crack Extension in a Piping Elbow Using Fracture Mechanics Techniques
2. The effect of temperature and neutron irradiation upon the fatigue-crack propagation behavior of ASTM A533-B steel
3. Fatigue-crack propagation in unirradiated and irradiated ASTM A533-B steel at low cyclic frequency
4. Fatigue Crack Growth Resistance of Several Neutron Irradiated Pressure Vessel Steels and Welds
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1. Crack growth prediction for irradiated stainless steels under the combined fatigue-creep loading;Theoretical and Applied Fracture Mechanics;2020-10
2. Effect of Light Water Reactor Water Environments on the Fatigue Life of Reactor Materials;Journal of Pressure Vessel Technology;2017-10-06
3. The radiation swelling effect on fracture properties and fracture mechanisms of irradiated austenitic steels. Part I. Ductility and fracture toughness;Journal of Nuclear Materials;2016-11
4. The radiation swelling effect on fracture properties and fracture mechanisms of irradiated austenitic steels. Part II. Fatigue crack growth rate;Journal of Nuclear Materials;2016-11
5. Irradiation Damage;Materials for Nuclear Plants;2012-09-22
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