Three-dimensional overall calculations are set up with the SYNTRON/VOID program as whole core calculations on the Dresden 1 reactor. The utility of the methods used for the production of box average cross sections on the basis of separate fuel box calculations with the CDB code are investigated. An alternative method for the determination of box average diffusion constants is proposed.
|Place of Publication||Roskilde, Denmark|
|Publisher||Risø National Laboratory|
|Number of pages||17|
|Publication status||Published - 1973|