Report
Three-dimensional boiling-water reactor neutron flux calculations on the basis of homogenized fuel box cross sections
Three-dimensional overall calculations are set up with the SYNTRON/VOID program as whole core calculations on the Dresden 1 reactor. The utility of the methods used for the production of box average cross sections on the basis of separate fuel box calculations with the CDB code are investigated. An alternative method for the determination of box average diffusion constants is proposed.
Language: | English |
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Publisher: | Risø National Laboratory |
Year: | 1973 |
Series: | Risø-m |
ISSN: | 04186435 |
Types: | Report |