Publication Type
Conference Paper
Publication Date
Volume
N/A
Conference Name
Workshop on Advanced Reactors with Innovative Fuels (ARWIF-2008)
Conference Location
Tsuruga/Fukui, Japan
Conference Date
-
Abstract
Within the framework of the OECD/NEA Expert Group on Reactor-based Plutonium disposition (TFRPD), a fuel modeling code benchmarks for MOX fuel was initiated. This paper summarizes the calculation results provided by the contributors for the first two fuel performance benchmark problems. A limited sensitivity study of the effect of the rod power uncertainty on code predictions of fuel centerline temperature and fuel pin pressure also was performed and is included in the paper