VERIFICATION OF THE OpenMC HOMOGENIZED MYRRHA-1.6 CORE MODEL

The OpenMC code is being employed both as a multi-group nodal macroscopic cross-section generator and reference Monte Carlo (MGMC) solution. aim to do neutronic benchmark verification study versus deterministic model (based on the MYRRHA-1.6 core) performed by PHISICS simulator. MYRRHA, novel research accelerator driven system concept that also foreseen work critical configuration, offers rich opportunity of testing state-of-the art methods for reactor physics analysis due its strong heterogeneous configuration utilized thermal fast spectra irradiation purposes. original core representing formed 169 assemblies, was launched in producing homogenous that, when executed mode, it produced k eff differs almost 500 pcm from case. This means future, such approximation should correct cross-sections preserve reaction rates order match those ones model. Nevertheless, MGMC mode operation offered could be exploited verify simulators. By inputting same into transport solver toolkit, showed difference 171 eigenvalue while comparing counterpart. Also, local energy-integrated profiles neutron flux maximum relative between methodologies 15% 1%, respectively. capabilities can other methodologies.