Abstract
The RAPID ( RA dial power and burnup P rediction by following fissile I sotope D istribution in the pellet) model was developed to predict the radial distribution of power, burnup and fissionable nuclide densities in the LWR UO 2 fuel pellets to be used in the fuel performance analysis code. It considers the specific radial variations of the neutron reactions of all the fissionable nuclides as functions of burnup and 235 U enrichment in the pellet. Comparison of the RAPID prediction with the measured data of the irradiated fuels and the predicted results by other codes showed good agreement, and therefore, the RAPID model can be used for UO 2 fuel of up to 10 w/o 235 U enrichment and 150 MWD/(kg U) pellet average burnup under the LWR environment.
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