CALCULATION OF THE NEUTRON LIFETIME BY THE FIRST-COLLISIONS PROBABILITY METHOD

The calculation of the neutron lifetime by the first-collisions probability method for nuclear power facilities which are described by a universal geometry is described. A derivation of the corresponding matrix approximations is presented. Algorithms for calculating the matrix elements using a universal geometric module, which, for example, is used in programs for performing Monte Carlo calculations of particle transfer, are proposed; MCU serves as an example of such a program. It is shown that the additional time required to calculate the neutron lifetime will not greatly slow down the calculations performed by the first-collisions probability method.