The internal pressurization creep of Zr alloys for spent-fuel dry storage feasibility
Author:
- 1 September 2000
- journal article
- Published by Springer Nature in JOM
- Vol. 52 (9) , 34-38
Abstract
No abstract availableKeywords
This publication has 29 references indexed in Scilit:
- Significance and Role of Deformation Micromechanisms in Life-Predictive Modeling of Aging StructuresApplied Mechanics Reviews, 1993
- The applicability of the strain-hardening rule to creep deformation of Zircaloy fuel cladding tube under dry storage conditionJournal of Nuclear Materials, 1991
- Creep deformation and rupture properties of unirradiated Zircaloy-4 nuclear fuel cladding tube at temperatures of 727 to 857 KJournal of Nuclear Materials, 1990
- Creep deformation of an unirradiated zircaloy nuclear fuel cladding tube under dry storage conditionsJournal of Nuclear Materials, 1990
- The irradiation creep and growth phenomenaJournal of Nuclear Materials, 1988
- LWR Spent Fuel Storage BehaviourJournal of Nuclear Materials, 1986
- Creep damage in zircaloy-4 at LWR temperaturesJournal of Nuclear Materials, 1979
- Creep transients in zircaloy claddingScripta Metallurgica, 1979
- Deformation mechanism mapping of α-Zr and zircaloy-2Journal of Nuclear Materials, 1975
- On the question of void formation in neutron irradiated zirconiumScripta Metallurgica, 1972