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Revision of the Transuranus PUREDI Model

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The Transuranus PUREDI model calculates the plutonium redistribution across the fuel pellet due to thermal diffusion. This phenomenon is particularly significant in oxide fuels for fast breeder reactors (FBR) where temperatures and temperature gradients are extremely high. The first version of PUREDI was developed and implemented as a stand-alone model. Since plutonium redistribution due to transport can lead to significant modifications of the radial power profile, a coupling of the PUREDI model with TUBRNP (recently extended for FBRs) is needed to correctly predict the fuel temperature. To this purpose, a revision of PUREDI has been proposed and the main features will be outlined in this report.
2012-08-27
Publications Office of the European Union
JRC70121
978-92-79-24905-1 (print),    978-92-79-24906-8,   
1018-5593 (print),    1831-9424 (online),   
EUR 25325 EN,    OP LC-NA-25325-EN-C (print),    OP LC-NA-25325-EN-N (online),   
https://publications.jrc.ec.europa.eu/repository/handle/JRC70121,   
10.2789/1361 (print),    10.2789/14043 (online),   
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