An effective solution scheme of a three-dimensional reactor core model in hexagonal geometry

Abstract
An efficient algorithm for a more accurate solution of the few-group coarse-mesh diffusion equations in hexagonal-z geometry has been developed and verified. The finite-difference type nodal approach to solve the diffusion equations, the theoretically well-founded effective inner iteration method and the optimized multilevel solution strategy are the essential features of this algorithm, applied in neutronics design code HEXAB-3D. The original and improved Fortran 77 program version, adapted ...

Title of program: HEXAB-3D
Catalogue Id: ACTS_v1_0

Nature of problem
HEXAB-3D computer code [1,2] calculates the effective multiplication factor, the group neutron flux and power distributions, the peaking factors, the control rod worth etc. in nuclear power reactors with hexagonal core configuration and heterogeneous structure in axial direction. There are two options for the diffusion equation solution in horizontal plane: 30degree -sector of reactor core (with reflective conditions on the internal reactor boundaries) or full core.

Versions of this program held in the CPC repository in Mendeley Data
ACTS_v1_0; HEXAB-3D; 10.1016/0010-4655(94)90126-0

This program has been imported from the CPC Program Library held at Queen's University Belfast (1969-2019)