The application of digital computers to nuclear-reactor design

The paper reviews the main computational problems arising in the design of a nuclear power reactor. The numerical-mathematical methods available are described briefly in two broad classes, namely the discrete-particle (Monte Carlo) treatment of the neutron-transport problems and the analytical methods based on the transport equation. The use of digital computers in the different methods is discussed in general terms and three examples are considered in more detail: the calculation of the thermal utilization factor for a lattice by the spherical harmonics method, the direct numerical solution of the 2-group diffusion equations for a cylindrical reactor and the calculation by Monte Carlo methods of the resonance escape probability for a graphite-uranium lattice. Finally there is a discussion of the standard of performance of computers likely to be required by nuclear engineers.