Calculation of Gamma Fluxes in CANDU Lattices

Abstract

The discrete ordinates codes ANISN and DOT have been used to calculate gamma fluxes in the lattice of a CANDU reactor. The libraries of cross sections used and details of the calculations are described.

The gamma fluxes are used to calculate where gamma energy is deposited in the lattice, photoneutron sources in the shutdown reactor and the gamma response of the platinum self-powered detectors. Comparisons with measured values show reasonable agreement.