Flow and fracture of alloys in the fusion environment
- 31 December 1981
- journal article
- Published by Elsevier in Journal of Nuclear Materials
- Vol. 104, 1305-1314
- https://doi.org/10.1016/0022-3115(82)90780-2
Abstract
No abstract availableThis publication has 14 references indexed in Scilit:
- Fatigue-Crack Growth Behavior in Fast-Neutron-Irradiated Ferritic Steels and WeldmentsJournal of Engineering Materials and Technology, 1980
- Tensile properties of type 316 stainless steel irradiated in a simulated fusion reactor environmentJournal of Nuclear Materials, 1979
- Critical fracture stress and fracture strain models for the prediction of lower and upper shelf toughness in nuclear pressure vessel steelsMetallurgical Transactions A, 1979
- FLOW LOCALIZATION AND THE FRACTURE TOUGHNESS OF HIGH STRENGTH MATERIALSPublished by Elsevier ,1978
- Slip morphology in dispersion hardened materialsMaterials Science and Engineering, 1976
- Yielding on inclined planes at the tip of a crack loaded in uniform tensionJournal of the Mechanics and Physics of Solids, 1976
- The effect of fast neutron irradiation upon the fatigue-crack propagation behavior of two austenitic stainless steelsJournal of Nuclear Materials, 1976
- Interpretation of Irradiation Effects on the Fracture Toughness of a Pressure Vessel Steel in Terms of Crack Tip Stress AnalysisJournal of Engineering Materials and Technology, 1976
- On the relationship between critical tensile stress and fracture toughness in mild steelJournal of the Mechanics and Physics of Solids, 1973
- Mechanisms of fatigue crack growth in low alloy steelActa Metallurgica, 1973