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.
|Number of pages||41|
|State||Published - Dec 1962|
|Publisher||Studiecentrum voor Kernenergie|