Article ID | Journal | Published Year | Pages | File Type |
---|---|---|---|---|
1729940 | Annals of Nuclear Energy | 2009 | 5 Pages |
Abstract
Within the framework of the OECD/NEA Expert Group on Reactor-based Plutonium disposition (TFRPD), fuel modeling code benchmarks for MOX fuel were 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.
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Authors
L.J. Ott, Terje Tverberg, Enrico Sartori,