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Reactivity and flux calculations using MCNP for...
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Reactivity and flux calculations using MCNP for heavy-water experiments in the ZED-2 critical facility using low-enriched uranium fuel bundles

Abstract

Experiments were performed in the ZED-2 (Zero Energy Deuterium) critical facility at AECL Chalk River Laboratories using a 24-cm pitch square lattice of 52 channels of heavy-water-moderated ACR-LEU and CANFLEX-LEU 43-element low-enriched uranium fuel bundles. These fuel bundles were cooled with H 2O, air (void) or a checkerboard pattern of H2O and air coolants. MCNP was used to calculate the reactivity and global flux distributions, which were …

Authors

Wong FC; Pencer J; Bromley BP; Atfield J; Zeller M

Volume

1

Pagination

pp. 115-124

Publication Date

January 1, 2010

Conference proceedings

International Conference on the Physics of Reactors 2010 Physor 2010