The Effect of Fast-Neutron Irradiation on the Fatigue-Crack Growth Behavior of Several Austenitic Stainless Steels and Weldments
Author:
Affiliation:
1. Westinghouse Hanford Company, Richland, Washington 99352
Publisher
Informa UK Limited
Subject
Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics
Link
https://www.tandfonline.com/doi/pdf/10.13182/NT86-A33821
Reference24 articles.
1. Fatigue-Crack Propagation in Fast-Neutron-Irradiated Types-304 and -316 Stainless Steels
2. Effect of Neutron Irradiation on Fatigue Crack Propagation in Types 304 and 316 Stainless Steels at High Temperatures
3. The effect of fast neutron irradiation upon the fatigue-crack propagation behavior of two austenitic stainless steels
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1. Fatigue crack growth in 316 type stainless steel at temperatures and displacement damage rates representative for the first wall loading;Journal of Nuclear Materials;1992-09
2. Influence of radiation damage on the cyclic crack resistance of austenitic steels and alloys (review);Strength of Materials;1991-07
3. Mechanical Properties of Neutron Irradiated Fuel Cladding Tubes;Journal of Nuclear Science and Technology;1991-04
4. Fracture Toughness of Irradiated Stainless Steel Alloys;Nuclear Technology;1988-09
5. Fatigue-crack propagation and fracture toughness behavior of cast stainless steels;Engineering Fracture Mechanics;1988-01
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