Three-dimensional boiling-water reactor neutron flux calculations on the basis of homogenized fuel box cross sections

Hans Hvidtfeldt Larsen

Three-dimensional boiling-water reactor neutron flux calculations on the basis of homogenized fuel box cross sections

Hans Hvidtfeldt Larsen

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Abstract

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.

Original language	English

Place of Publication	Roskilde, Denmark
Publisher	Risø National Laboratory
Number of pages	17
Publication status	Published - 1973

Series	Risø-M
Number	1616
ISSN	0418-6435

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Risø-M-1616

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Ris m 1616Final published version, 449 KB

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AB - 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.

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M3 - Report

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BT - Three-dimensional boiling-water reactor neutron flux calculations on the basis of homogenized fuel box cross sections

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ER -

Three-dimensional boiling-water reactor neutron flux calculations on the basis of homogenized fuel box cross sections

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