Abstract
Various modifications of the Monte Carlo method have been proposed to reduce the statistical error in the results of calculations of the neutron-flux functionals [i]. Most of these employ nonanalog modeling of the particle-transfer process. However, because of the universality and simplicity of their mathematical formulation, analog methods remain the basic instrument in the practice of reactor calculations. The present work proposes an economical method of combining the estimate of the neutron-flux functionals obtained using correlated selection with the determinate estimate for a simplified system. As an example, the problem of calculating the reaction rate in a heterogeneous reactor with leakage is considered. This situation is typical for the identification of integral experiments on critical piles. Analog Monte Carlo methods for calculating the neutron-physics parameters of nuclear reactors are fomulated using the transfer equation [i]
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