Calcul des distributions de temperature dans les plaques combustibles de BR2 avec decollement du gainage ou inclusion d'uranium pur

The equations of the heat diffusion are solved with the help of a neutron diffusion code. This method is used for the study of two kinds of defects in the fuel plates of the BR2 reactor: cIad bonding defect and uranium inclusion . The corresponding hot spot factors are computed . Defects of circular and rectangular section are studied.