A MULTI-DIMENSIONAL, MULTIGROUP, MULTIREGION, NEUTRON DIFFUSION CODE (ITERATIVE-VARIATIONAL APPROACH)
Technical Report
·
OSTI ID:4070053
The program LOUlSE III, in FORTRAN for the IBM 7090, calculates the criticality constant and critical fluxes of multiregion (up to 25) reactors in the multigroup (up to 10) approximation. Calculations can be performed in up to 7 dimensions, and an iterative-variational technique is used. The diffusion differential equations considered are included, together with a sample problem and the FORTRAN listing. LOUISE III has given results in agreement with WHIRLAWAY, while requiring a much shorter execution time. (auth)
- Research Organization:
- Milan. Universita
- NSA Number:
- NSA-18-015131
- OSTI ID:
- 4070053
- Report Number(s):
- EUR-532.c
- Country of Publication:
- Country unknown/Code not available
- Language:
- English
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