Creep deformation of an unirradiated zircaloy nuclear fuel cladding tube under dry storage conditions
- 1 May 1990
- journal article
- Published by Elsevier in Journal of Nuclear Materials
- Vol. 171 (2-3) , 381-388
- https://doi.org/10.1016/0022-3115(90)90384-y
Abstract
No abstract availableThis publication has 4 references indexed in Scilit:
- Thermal creep of zircaloy-4 cladding under internal pressure.Journal of Nuclear Science and Technology, 1987
- Accelerated High-Temperature Tests with Spent PWR and BWR Fuel Rods Under Dry Storage ConditionsNuclear Technology, 1986
- LWR Spent Fuel Storage BehaviourJournal of Nuclear Materials, 1986
- Some Observations on Time-Hardening and Strain-Hardening Rules for Creep in Zircaloy-2Nuclear Technology, 1981