Corrosion fatigue in pressure vessel steels for light water reactors
- 18 July 1979
- journal article
- Published by Taylor & Francis in Metal Science
- Vol. 13 (7) , 396-401
- https://doi.org/10.1179/msc.1979.13.7.396
Abstract
No abstract availableThis publication has 9 references indexed in Scilit:
- Effect of grain size and temperature on fatigue crack propagation in A533 B steelEngineering Fracture Mechanics, 1978
- SEAN ReportEos, 1978
- Fatigue Crack Growth Characteristics of A533 Grade B Class I Plate in an Environment of High-Temperature Primary Grade Nuclear Reactor WaterJournal of Pressure Vessel Technology, 1977
- Sustained load crack growth in A533B-1 steel under neutron irradiation in a water environmentNuclear Engineering and Design, 1976
- Fatigue Crack Growth in SA508-CL2 Steel in a High Temperature, High Purity Water EnvironmentJournal of Engineering Materials and Technology, 1974
- The influence of stress intensity and microstructure on fatigue crack propagation in ferritic materialsEngineering Fracture Mechanics, 1972
- Effect of stress cycle asymmetry on fatigue crack growthMaterials Science and Engineering, 1972
- Metallographic investigation on the cladding failure in the pressure vessel of a BWRNuclear Engineering and Design, 1971
- Hydrogen effects in an irradiated 1 % Cr, 12 % Mo pwr pressure vessel steelJournal of Nuclear Materials, 1965