Published 1994 | Version v1
Miscellaneous

Simulation of reactivity control devices in a CANDU-6 reactor using DRAGON

  • 1. Ecole Polytechnique, Montreal, PQ (Canada). Inst. de Genie Nucleaire
  • 2. Atomic Energy Control Board, Ottawa, ON (Canada)

Description

A full core calculation for a CANDU reactor generally requires the knowledge of the few group cross sections associated with a fuel cell (2-D geometry) along with incremental cross sections representing the effect of inserting reactivity control devices in a supercell (3-D geometry). However, one generally observes that the supercell calculation with the reactivity device absent leads to a multiplication constant which may differ considerably from that obtained using the cell calculation. Here we propose to use DRAGON to perform both the cell and supercell calculation in a coherent fashion. First a cell calculation will be considered using DRAGON to generate multigroup fuel cross sections. This will be followed by an homogenization of the 2-D fuel properties to a 3-D supercell containing only the fuel using the SPH equivalence technique. One then expects that the few groups incremental cross section obtained using these multigroup fuel properties will represent more closely the effect of a given reactivity device in the reactor. (author). 6 refs., 4 tabs., 2 figs

Part of:
Proceedings of the 1994 nuclear simulation symposium

Additional details

Publishing Information

Imprint Title
Proceedings of the 1994 nuclear simulation symposium
Imprint Pagination
290 p.
Journal Page Range
p. 113-121.
Report number
INIS-mf--14840

Conference

Title
1994 nuclear simulation symposium.
Dates
12-14 Oct 1994.
Place
Pembroke, ON (Canada).

Optional Information