Program for computing the alternatives of fuel supply for the Czechoslovak nuclear power

The algorithm of a computer code and its formulation in FORTRAN IV are shown for determining the basic characteristics of fuel supply in a nuclear program involving both thermal and fast reactors. The program is formulated such that on the basis of defined criteria, it chooses one of the five reactor types at a moment of required output increase. The choice is made during calculation. The possibility is offered to respect the time of fuel circulation either by the external cycle or by spent uranium recycling, and to choose the onset of fast reactors. (author)