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Manuscript Title: An effective solution scheme of three-dimensional reactor core model in hexagonal geometry.
Authors: K.N. Ivanov, M.A. Manolova, T.G. Apostolov
Program title: HEXAB-3D
Catalogue identifier: ACTS_v1_0
Distribution format: gz
Journal reference: Comput. Phys. Commun. 82(1994)1
Programming language: Fortran.
Computer: IBM PC.
Operating system: MS-DOS 5.0.
RAM: 170K words
Word size: 16
Peripherals: disc.
Keywords: Reactor systems, Diffusion, Few-group, Neutron, Coarse-mesh, Hexagonal geometry, Nuclear power reactor.
Classification: 22.

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.

Solution method:
The three-dimensional multigroup diffusion equations are solved using nine-point mesh-centered finite-difference approximation. The standard inner-outer iterative strategy is applied. Inner iterations are solved using incomplete factorization techniques: the AGA two- sweep iterative method and the modified two-sweep iterative method MAGA [1,2], both accelerated by the double successive overrelaxation procedure. The power method, combined with two- or three-term Chebyshev polynomial acceleration for outer iterations is applied in the code.

The following restrictions, determined by our hardware resources are imposed on individual problem parameters: maximum of 10 energy groups. 30 horizontal layers and 100 material compositions. For users with access to greater computing resources the easing of these limitations is possible.

Unusual features:
Related programs - DAFDEF: serves for data array input-output operations with direct access files.

Running time:
The CPU time used in the Keff calculations for 3D reactor models with 4 energy groups and for the following convergence criteria: between successive iterations - epsilonPhi <=10**-4 and on Keff - epsilonKeff <=10**-6 on IBM PS/2 (386) (1x10**6 floating point oper.per sec) is about: 80 sec for SNR-300 Benchmark [3], B1 problem (full core) with 7940 mesh points; 201 sec for BN-1600 Benchmark [4] (full core) with 21567 mesh points.

[1] K.N.Ivanov, T.G.Apostolov and M.A.Manolova, in: Proc.of ITM on Advances in Mathematics, Computations and Reactor Physics, USA, 1991, Vol. 5 (ANS, Pittsburgh, 1991) p.30.2 10-1.
[2] K.N.Ivanov, T.G.Apostolov and M.A.Manolova, Nucl.Sci.Eng. 114 (2) (1993) 176.
[3] G. Buckel, K. Kuefner and B. Stehle, Nucl.Sci.Eng., 64(1977)75.
[4] V. Matveev et al., in: Proc.of Specialist's Meeting on Methods and Codes for Fast Reactor Calculations, Rumania, 1985 (INER, Bucharest, 1986) p.8.1.