A thermal nuclear reactor as an analog of ADS systems with internal sources of neutrons

Abstract

The average magnitudes of random values and their dispersions are for many processes known in science and engineering estimated by choosing the appropriate probabilistic processes. The instantaneous intensities of a process are then simulated. At the same time, mathematical expectations of random values and their dispersions can often be exactly or approximately presented in the form of analytical functions of translational intensities. This is a rather common approach, so it is evident that it can also be used in describing processes that occur during the interaction between neutrons and neutron-multiplying media in power reactors of various types. In this work, the above problem is solved for a thermal nuclear reactor.