Creation of a computer program for calculation the location- and time-dependent core density in spherical fuel assemblies

Automatic translation: An exact calculation of the temperature distribution in spherical fuel elements is therefore only possible with knowledge of the local and time-dependent fissile material concentrations possible. The calculation program NUKLI - a coupling of the proven programs THERMOS and BURN UP - supplies the nuclide concentrations Ni (r,t) and thus creates the basis for more precise temperature calculations. The neutron flux within a fuel sphere is the integral transport equation and the kernel densities calculated according to the well-known Aborand equations in difference notation. The idea ofcoupling a spectral program with a burn program is not new. The programs FEVER and MAFIA V.S.O.P. are based on the same thought. you calculate the neutron flux according to the diffusion theory via a cell calculation with 4 energy groups, one of which is thermal includes energy range. The burnup equations are given in these programs also solved in difference notation. The structure and mode of operation of the 1-dimensional program NUKLI. The appendix contains a precise input description with an associated Example. In this part are all necessary for the user documents compiled.