Development and test of a hybrid probabilistic-deterministic framework based on the interface current method
Paper i proceeding, 2019
This paper investigates the feasibility of performing reactor physics calculations using a hybrid neutron transport methodology. In the presented implementation, the interface current method is used as the deterministic framework, for which the necessary probabilities appearing in the
method are estimated in advance using the probabilistic Monte Carlo code Serpent2. Two grids are used: one fine grid for estimating the scalar neutron flux and a coarse grid for computing the neutron currents on this grid. Once the probabilities have been estimated, the solutions on both grids are computed deterministically and simultaneously. The main advantage of this implementation lies with the fact that the modelling of possible complex geometries is left to the Monte Carlo solver. In addition, since only within cells probabilities are required, the estimation of such probabilities represents a task having an acceptable computing cost. Several two-dimensional test cases were developed for benchmarking the framework in two energy
groups. For single assembly calculations in an infinite lattice, the deviation of the dominant eigenvalue is smaller than typically 50 pcm. Concerning the spatial distribution of the flux, some acceptable agreement was also obtained, with relative deviations generally smaller than 6%. In some other cases considering a checkerboard pattern of fuel assemblies, though, higher discrepancies were noticed. It is believed that such discrepancies could be alleviated by implementing a finer resolution in space, angle and energy of the framework. This feasibility study demonstrates the viability of the proposed computational route.
nuclear reactor calculations