BENCHMARKING OF THE SERPENT 2 MONTE CARLO CODE FOR FUSION NEUTRONICS APPLICATIONS

Analyses of radiation fields resulting from a deuterium-tritium (DT) plasma in fusion devices is critical input to the design and validation many aspects reactor design, including, shielding, material lifetime remote maintenance requirements/scheduling. Neutronics studies, which perform in-depth analysis are typically performed using transport codes such as MCNP, TRIPOLI, Serpent, FLUKA OpenMC. The Serpent 2 Monte-Carlo code, developed by VTT Finland, focus this work seeks benchmark code for applications. application specific requires performance an energy range, geometrical description, significantly differs conventional nuclear fission analysis, was originally developed. A model Frascati Neutron Generator (FNG) Helium Cooled Pebble Bed (HCPB) mock up experiment has been prepared calculated results compared against experimental data, well reference Monte Carlo MCNP. extended DEMO with HCPB blanket concept. For model, flux, heating, tritium production DPA calculated, all integral responses analysis. In general, very good agreement demonstrated both benchmarks, any discrepancies pinpointed different physics models implemented.