Properties of zirconium base cladding materials-corrosion and hydrogen pickup
- 31 December 1972
- journal article
- Published by Elsevier in Nuclear Engineering and Design
- Vol. 21 (2), 200-211
- https://doi.org/10.1016/0029-5493(72)90073-8
Abstract
No abstract availableKeywords
This publication has 3 references indexed in Scilit:
- The behaviour of defective reactor fuelNuclear Engineering and Design, 1972
- UO2 properties affecting performanceNuclear Engineering and Design, 1972
- Effects of irradiation on the oxidation of zirconium alloys in high temperature aqueous environments: A reviewJournal of Nuclear Materials, 1968