Technique and programs for two- and three-dimensional calculations of energy release fields in reactors with hexagonal geometry

Described are the technique and programs fot two-and three-dimensional calculations of energy release fields in reactors with hexagonal geometry. The neutron transport is described by two-group diffusion equations, which are transformed to four-point finite-difference form for two-dimensional geometry, and to six-point form for three-dimensional calculations. Considered are the methods of iteration process acceleration, namely: the Viland method which allows to reduce the calculation time by 6-8 times for thermal reactors and by 4-6 times for fast reactors; and the method of spectrum double shift, which reduce the calculation time by 4 times. The acceleration methods used quarantee the stability of calculation and acceleration at any skews of energy release fields in reactors. The programs are written in the FORTRAN language for the BESM-6 computer