Fatigue crack propagation in neutron irradiated type 304 and type 308 stainless steel plate and weld materials
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference6 articles.
1. Creep-Fatigue Crack Propagation in Austenitic Stainless Steel
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1. On load-following operations of small modular reactors;Progress in Nuclear Energy;2024-08
2. Effect of Light Water Reactor Water Environments on the Fatigue Life of Reactor Materials;Journal of Pressure Vessel Technology;2017-10-06
3. Intergranular crack tip oxidation mechanism in a nickel-based superalloy;Materials Science and Engineering: A;1992-06
4. Influence of radiation damage on the cyclic crack resistance of austenitic steels and alloys (review);Strength of Materials;1991-07
5. The Effect of Fast-Neutron Irradiation on the Fatigue-Crack Growth Behavior of Several Austenitic Stainless Steels and Weldments;Nuclear Technology;1986-07
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