Developing a Nuclear Neutronic Code in Rectangular, Triangular and Cylindrical Geometry

A three-dimensional reactor static code for calculation of flux, power, multiplication factor and also power peaking factor in rectangular, triangular and cylindrical geometry core has been developed and benchmarked. For solution of the time independent neuron diffusion equation a finite difference method was used. To solve the equation with finite difference method, the speed of the applied numerical calculation is a major subject of interest, especially when the number of nodes increases. For this reason using an appropriate method to make the calculation faster is considered as the main priority. The aim of this paper is to present this three-dimensional nuclear reactor code with an emphasis made on the comparison between the advanced iterative algorithms in this code.