THE TWENTY GRAND PROGRAM FOR THE NUMERICAL SOLUTION OF FEW-GROUP NEUTRON DIFFUSION EQUATIONS IN TWO DIMENSIONS
The TWENTY GRAND program for the IBM 7090 is capable of solving neutron diffusion problems in cylindrical or slab geometry for one to six groups. Up to 3000 mesh points may be used. Neutron transfer from any group to any other group is permitted. Leakage in the third dimension in X-Y geometry may be treated by a buckling which can vary with region and group. Three types of symmetry conditions may be handled automatically. The zero flux, zero derivative, and logarithmic boundary conditions are available. Normalization of fluxes to an arbitrary input power is allowed. The fission source distribution and the adjoint fluxes and associated integrals may be computed at the user's option. The number of mesh sweeps permitted is stated as input. The average running time in seconds per iteration per group is approximately 0.0035. (auth)
- Research Organization:
- Oak Ridge National Lab., Tenn.
- DOE Contract Number:
- W-7405-ENG-26
- NSA Number:
- NSA-16-010394
- OSTI ID:
- 4792907
- Report Number(s):
- ORNL-3200
- Country of Publication:
- United States
- Language:
- English
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