DRAGON SIMULATION OF RADIAL PWR REFLECTOR
CNS 24th Nuclear Simulation Symposium - 2012 October 15-16


Presented at:
CNS 24th Nuclear Simulation Symposium
2012 October 15-16
Location:
Ottawa,Canada
Session Title:
Technical 5: Reactor Physics

Authors:
Najoua Bejaoui (École Polytechnique de Montréal)
Guy Marleau (École Polytechnique de Montréal)
  

Abstract

In order to reduce the uncertainties in PWR core power distribution calculations carried out by a core code, an accurate model of the radial PWR reflector is required. The method we propose in this paper is to use a 2D transport calculation for a multi-assembly representation of the core to evaluate two groups cross sections and diffusion coefficients for the homogenized reflector. Those parameters are then injected in the core calculation to solve the diffusion equation. Here, we will compare the results obtained using the lattice code DRAGON for two groups reflector parameters with those published in the literature for the TMI-PWR benchmark.

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