Experimental system for studying temperature gradient-driven fracture of oxide nuclear fuel out of reactor
Author:
Affiliation:
1. Department of Mechanical Engineering, University of South Carolina, 300 Main St., Columbia, South Carolina 29205, USA
2. Westinghouse Electric, Bränslegatan 1, 721 36 Västerås, Sweden
3. Idaho National Laboratory, Idaho Falls, Idaho 83402, USA
Funder
Nuclear Energy University Program
Publisher
AIP Publishing
Subject
Instrumentation
Link
http://aip.scitation.org/doi/am-pdf/10.1063/1.5119361
Reference8 articles.
1. Multi-Dimensional Simulation of LWR Fuel Behavior in the BISON Fuel Performance Code
2. Mechanical behaviour modelling of fractured nuclear fuel pellets
3. Modelling explicit fracture of nuclear fuel pellets using peridynamics
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