학술논문

Modeling Creep Rupture of Zirconium Alloys
Document Type
Conference
Author
Source
Conference: 8th International Symposium on Plasticity and its Current Applications, Whistler Resort, British Columbia (CA), 07/17/2000--07/21/2000; Other Information: PBD: 8 Apr 2000
Subject
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
36 MATERIALS SCIENCE CREEP
DIFFUSION
DRY STORAGE
MODIFICATIONS
NUCLEAR FUELS
PLASTICITY
REGULATIONS
RUPTURES
SAFETY STANDARDS
STORAGE
ZIRCONIUM ALLOYS
Language
English
Abstract
Safe interim dry storage of spent nuclear fuel (SNF) must be maintained for a minimum of twenty years according to the Code of Federal Regulations. The most important variable that must be regulated by dry storage licensees in order to meet current safety standards is the temperature of the SNF. The two currently accepted models to define the maximum allowable storage temperature for SNF are based on a diffusion controlled cavity growth (DCCG) failure mechanism for the cladding. Although these models are based on the same fundamental failure theory (DCCG), the researchers who developed the models made different assumptions, including selection of some of the most critical variables in the DCCG failure equation. These inconsistencies are discussed together with recommended modifications to the failure models based on recent data.