Analysis of Irradiation Growth and Multiaxial Deformation Behavior of Nuclear Fuel Cladding
- 1 January 1979
- book chapter
- Published by ASTM International
- p. 189-201
- https://doi.org/10.1520/stp36680s
Abstract
No abstract availableKeywords
This publication has 9 references indexed in Scilit:
- Irradiation-growth of zirconium-base alloys: Part IJournal of Nuclear Materials, 1978
- The nature of dislocation loops in neutron irradiated zirconiumJournal of Nuclear Materials, 1977
- Irradiation Growth of ZircaloyPublished by ASTM International ,1977
- The contribution of dislocation loops to radiation growth and creep of Zircaloy - 2Journal of Nuclear Materials, 1975
- The effect of a zirconium strength differential on cladding collapse predictionsJournal of Nuclear Materials, 1975
- Localized Deformation and Fracture in Neutron Irradiated Zircaloy-2Metallurgical Transactions, 1974
- A simulation of texture development in f.c.c. metalsPhilosophical Magazine, 1972
- Texture and anisotropy of zirconium in relation to plastic deformationCanadian Metallurgical Quarterly, 1972
- Zur Darstellung allgemeiner TexturenInternational Journal of Materials Research, 1965