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Calculation of the void reactivity of CANDU lattices using thescalecode system

Authors
Journal
Nuclear Engineering and Design
0029-5493
Publisher
Elsevier
Publication Date
Volume
159
Identifiers
DOI: 10.1016/0029-5493(95)01086-w
Disciplines
  • Mathematics

Abstract

Abstract The reactivity effect of coolant voiding in CANDU-type fuel lattices has been calculated with different methods using the scale code system. The known positive void reactivity coefficient of the original lattice was correctly obtained. A modified fuel bundle containing dysprosium and slightly enriched uranium to eliminate the positive reactivity effect was also calculated. Owing to the increased heterogeneity of this modified fuel the one-dimensional cylindrical calculation with XSDRN proved to be inadequate. Code options allowing bundle geometry were successfully used for the calculation of the strongly space dependent flux and spectrum changes which determine the void reactivity.

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