An Efficient Computational Technique for Thermal Reactor Transients

An accurate and computationally efficient numerical method for solving the two-group, multidimensional transient neutron diffusion equations with feedback is discussed. The method employs an approximation for the spatial shape of the thermal fluxes. The results of the test problems demonstrate that the convergence of the iteration scheme can be accelerated, and the resulting computing time can be greatly reduced while maintaining computational accuracy.