Initial-value problem for equations of reactor kinetics with delayed neutrons and its numerical solution by the Monte Carlo method

Based on the transport equation, the Cauchy problem for reactor kinetics equations was studied making allowance for delayed neutrons. A proof was obtained that the solution exists and is unique. Several types of random processes and random variables are given to assist the numerical treatment of the problem by the Monte Carlo method. It is demonstrated that the random variables have the expected finite values and dispersions and that they provide an unbiassed estimate of the solution. (author). 5 refs