Variation of the mechanical properties of irradiated Hastelloy N with strain rate
- 31 May 1969
- journal article
- Published by Elsevier in Journal of Nuclear Materials
- Vol. 31 (1) , 67-85
- https://doi.org/10.1016/0022-3115(69)90044-0
Abstract
No abstract availableKeywords
This publication has 13 references indexed in Scilit:
- Growth op grain boundary bubbles in materials containing inert gases: A comment on the paper of russell and velaJournal of Nuclear Materials, 1967
- A theory of grain boundary degeneration in materials which contain an inert gasJournal of Nuclear Materials, 1967
- The observation of helium bubbles in irradiated 20 % Cr-25 % Ni-Ti stainless steelJournal of Nuclear Materials, 1966
- Reduction in Ductility of Austenitic Stainless Steel after IrradiationNature, 1965
- The production of hydrogen and helium in metals during reactor irradiationJournal of Nuclear Materials, 1965
- Effect of Elevated-Temperature Irradiation on Hastelloy NNuclear Applications, 1965
- The effects of neutron irradiation at elevated temperatures on the tensile properties of some austenitic stainless steelsJournal of Nuclear Materials, 1963
- The growth of grain-boundary voids under stressPhilosophical Magazine, 1959
- A theory of the fracture of metalsAdvances in Physics, 1957
- Growth of voids in metals during diffusion and creepActa Metallurgica, 1957