A Monte-Carlo Estimate of the Diffusion Coefficient for a CANDU Cell
Main Article Content
Abstract
In this paper, the radial diffusion coefficient for a CANDU cell is calculated by using the Monte Carlo code MCNP [1]. The calculation uses the conventional definition of the
diffusion coefficient which is based on the transport cross section. The latter is estimated from an MCNP simulation of the CANDU cell with a reflective boundary condition.
These MCNP-based two-group diffusion coefficients are compared to the corresponding
result obtained with the transport and depletion code HELIOS [2]. The calculations are
performed for two burnup states: 0 and 4 GWd/TU.
diffusion coefficient which is based on the transport cross section. The latter is estimated from an MCNP simulation of the CANDU cell with a reflective boundary condition.
These MCNP-based two-group diffusion coefficients are compared to the corresponding
result obtained with the transport and depletion code HELIOS [2]. The calculations are
performed for two burnup states: 0 and 4 GWd/TU.
Article Details
Section
Articles