Effect of Neutron Irradiation on Fatigue Crack Propagation in Types 304 and 316 Stainless Steels at High Temperatures
- 1 January 1973
- book chapter
- Published by ASTM International
- p. 493-508
- https://doi.org/10.1520/stp35471s
Abstract
No abstract availableThis publication has 5 references indexed in Scilit:
- Fatigue Crack Growth in Type 316 Stainless Steel at High TemperatureJournal of Engineering for Industry, 1971
- Fatigue-crack propagation behavior of type 304 stainless steel at elevated temperaturesMetallurgical Transactions, 1971
- Ductility Loss in Fast Reactor Irradiated Stainless SteelNuclear Applications and Technology, 1970
- Fatigue and Burst Tests on Irradiated In-Pile Stainless-Steel Pressure TubesNuclear Applications, 1965
- A Critical Analysis of Crack Propagation LawsJournal of Basic Engineering, 1963