3D hexagonal parallel code QuDiff for fast reactor critical parameters calculations

Applicable for high-performance computational environments parallel code QuDiff for fast reactor critical parameters calculations has been implemented based on a sequential version. A multigroup transport equation calculation method was build upon V.Ya.Goldin's quasi-diffusion method. For efficient algorithm construction it was suggested to use all the reactor assembly symmetries, possible for self-adjustable neutron-nuclear regime of operation. MPI was applied as a parallel interface. Domain decomposition method was utilized. Pipelined parallelization of transport equation has been used for its consistency with quasi-diffusion system of equations parallelization. Calculations of 3D active zone model of the BN-800 type reactor capable of operating in self-adjustable neutron-nuclear regime showed that parallel code QuDiff is highly scalable. It is assumed to use most of the results of this work in dynamical numerical simulation of fast reactors' active zones.