TRANSVERSE LEAKAGE SPECIFICATION IN MULTI-GROUP PSEUDO-ONE-DIMENSIONAL PROBLEMS
A method is described for specifying the transverse leakage (""buckling"") in each energy group of a multigroup solution of the neutron transport equation. As applied to a completely reflected finite cylindrical core, the method consists in using the calculated absorptions in the Fore and leakages from the core from a onedimensional multigroup run to calculate more exact group bucklings to be used in the next iteration in the other direction. The process is repeated until the buckling in each group in each direction converges. The converged value of the multiplication constant or the criticality parameter, if one is used, is found to be independent of the initial guess made for the axial or radial buckling. The IBM-704 multigroup sge diffusion code GNU was used in conjunction with this ""buckling iteration method"" to compute the equivalent spherical radii of a number of fully reflected finite cylindrical cores for which experimental data are available. These results are compared with those obtained by the use of other prescriptions for calculating the reactivity of cylindrical cores. There is a brief discussion of the extension of the buckling iteration method to other than cylindrical cores. (auth)
- Research Organization:
- General Motors Corp. Research Staff, Detroit
- NSA Number:
- NSA-13-003096
- OSTI ID:
- 4311000
- Report Number(s):
- GMR-107
- Country of Publication:
- Country unknown/Code not available
- Language:
- English
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