There is a settlement code ICC developed for the purpose of critical calculations throughout the campaign of research reactor IVV-2M. This code allows calculation of energy emission in separate cells (channels) of reactor’s core. Calculation is not possible in real time because of manual input of source data. The settlement code is implemented in FORTRAN programming language, therefore data have to enter in fixed input format. This causes an inconvenient and prolonged preparation of source data. The article describes a program able to solve problems of that kind. The program proposes simplified data preparation along with automatic data preparation in case of changing position of governing bodies of reactor.