Use of the Monte Carlo method in the process of interpretation of critical experiments for nuclear data evaluation

Test experiments for lattices of thermal uranium fuel reactors have been analyzed to refine nuclear data. The Monte Carlo method was used to calculate reaction rates and their perturbations. The calculational scheme is realized within the framework of the method of generations with the constant number of points. Results of the calculation performed for the TRX lattice with ratio of volumes of the moderator and fuel equal to 2.35 were used as an example. It is concluded that the methods considered permit to unambiguously bind experimental and calculational values and turn out to be especially effective for analyzing rod lattices of thermal reactors