Theory of the creep of zircaloy during neutron irradiation
- 30 April 1969
- journal article
- Published by Elsevier in Journal of Nuclear Materials
- Vol. 30 (3) , 249-270
- https://doi.org/10.1016/0022-3115(69)90241-4
Abstract
No abstract availableKeywords
This publication has 22 references indexed in Scilit:
- Unirradiated, in-pile and post-irradiation low strain rate tensile properties of zircaloy-4Journal of Nuclear Materials, 1969
- In-reactor creep of Zr-2.5 at % NbJournal of Nuclear Materials, 1968
- Radiation-enhanced relaxation in Zircaloy-4 and Zr/2.5 wt % Nb/0.5 wt % Cu alloysJournal of Nuclear Materials, 1968
- Application of the generalised theory of yielding creep to irradiation creep in Zirconium alloysJournal of Nuclear Materials, 1968
- Uniaxial in-reactor creep of Zirconium alloysJournal of Nuclear Materials, 1968
- The in-reactor creep of cold-worked Zircaloy-2 and Zirconium-2.5 wt % niobium pressure tubesJournal of Nuclear Materials, 1968
- Mechanisms for the in-reactor creep of Zirconium alloysJournal of Nuclear Materials, 1968
- Irradiation Creep in Several Metals and Alloys at 100° CNature, 1967
- The analysis of relaxation tests on specimens with inhomogeneous stressesBritish Journal of Applied Physics, 1966
- Effect of irradiation growth on the creep of uranium under a uniaxial loadPhilosophical Magazine, 1961