Article ID Journal Published Year Pages File Type
10644928 Journal of Nuclear Materials 2015 10 Pages PDF
Abstract
This article describes the first phase of the development of such a code, based on the well-established code FRAPCON 3.4, and in particular the correlations reviewed and chosen for the fuel material properties. The results of fuel temperature calculations with the code in its current state of development are shown and compared with data from a Th-MOX test irradiation campaign which is underway in the Halden research reactor. The results are good for fresh fuel, whereas experimental complications make it difficult to judge the adequacy of the code for simulations of irradiated fuel.
Related Topics
Physical Sciences and Engineering Energy Nuclear Energy and Engineering
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