Extension of the TRANSURANUS plutonium redistribution model for fast reactor performance analysis
The plutonium redistribution model (PUREDI) calculates the steady-state and transient radial plutonium
concentration as a function of the radial temperature profile and the time for mixed oxide fuels (MOX).
In the context of developing a TRANSURANUS version for Gen-IV fast reactor fuels, PUREDI has been
modified and extended to include the effects of the local power density profile and the oxygen-to-metal
ratio on plutonium transport. The model has been extensively verified by means of specific numerical
tests, and after incorporation in the TRANSURANUS fuel performance code, has been assessed on the
basis of post irradiation examinations of the SUPERFACT experiment, showing a good agreement with
the experimental data.
DI MARCELLO Valentino;
SCHUBERT Arndt;
VAN DE LAAR Jacques;
VAN UFFELEN Paul;
2012-05-16
ELSEVIER SCIENCE SA
JRC66717
0029-5493,
http://dx.doi.org/10.1016/j.nucengdes.2012.03.037,
https://publications.jrc.ec.europa.eu/repository/handle/JRC66717,
10.1016/j.nucengdes.2012.03.037,
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