Journal article Open Access
Vinai P.; Yi H.; Mylonakis A.; Demazière C.; Gasse B.; Rouchon A.; Zoia A.; Vidal-Ferrandiz A.; Ginestar D.; Verdu G.; Yamamoto T.
In the CORTEX project, several solvers are developed and applied to analyze neutron noise
problems. They are based on Monte Carlo and deterministic (higher-order transport and
diffusion) methods. For the study of their validity and limitations, an extensive verification
and validation work has been undertaken and includes the simulation of numerical exercises
and experiments. In the current paper the solvers are compared over two neutron noise
benchmarks defined in a 2-D simplified UOX fuel assembly, with Monte Carlo used as a
reference. In the two exercises, a global neutron noise source and a combination of stationary
perturbations of the various cross sections are respectively prescribed. The higher-order
neutron transport methods provide consistent results with respect to Monte Carlo. The
calculations obtained from the diffusion-based solvers show discrepancies that can be
significant, in particular close to the neutron noise source.