A METHOD FOR NUMERICAL SOLUTION OF THE NEUTRON DIFFUSION EQUATIONS IN HEXAGONAL GEOMETRY WITH A VARIABLE SPATIAL MESH
Technical Report
·
OSTI ID:4080283
From American Nuclear Society Meeting, New York, Nov. 1963. A mesh description technique that permits preparation of a computer program to solve the neutron diffusion equations in variable-mesh hexagonal geometry is discussed. The key concept, which could be employed in other geometries, is to specify by conventional means the internal details of each of several basic figures having interfaces in only two directions, then create final figures in the entire problem layout by translation, rotation, and, perhaps, reflection of these basic figures. The problem outline (illustrated) of the entire solution region permits bent sweep lines of constant length so that 120 deg periodicity may be obtained easily, and the Ritz method difference equations permit the implementation of the mesh description concept for a completely variable hexagonal mesh. The running time for the resulting code are comparable with those for rectangular geometry for the same number of points. (auth)
- Research Organization:
- Westinghouse Electric Corp. Bettis Atomic Power Lab., Pittsburgh
- DOE Contract Number:
- AT(11-1)-GEN-14
- NSA Number:
- NSA-18-011148
- OSTI ID:
- 4080283
- Report Number(s):
- WAPD-T-1610; CONF-187-51
- Country of Publication:
- United States
- Language:
- English
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