OpenMC-based high-fidelity model for the Moroccan TRIGA Mark II research reactor

The Moroccan TRIGA Mark II serves as a pivotal cornerstone in the advancement of nuclear science and technology within the region. Precise modeling is crucial for ensuring safe and efficient reactor operation. OpenMC, known for its versatility as a stochastic code with a powerful Python API, offers unique capabilities for reactor analysis, optimization, and automation. This makes OpenMC the ideal choice for neutronic analysis in the development of multi -physics models aimed at enhancing the accuracy and reliability of reactor analysis. Leveraging its Python interface, we have developed a high-fidelity model for the Moroccan TRIGA Mark II, enhancing modeling precision. A central element of this study involved making crucial modifications to OpenMC's source code, enabling the prompt method and calculating the ������������������ ������. These modifications are essential, representing a significant advancement in the capacity to conduct a comprehensive analysis of a wide range of critical neutronic parameters. These parameters include the neutron flux spectrum, ������������������������, control rods worth and core excess reactivity, and power peaking factors. The results exhibit strong agreement with the performed experimental measurements and MCNP6.2 calculations. The findings underscore the model's precision and reliability, making it a valuable asset for neutronic analysis and, particularly, for developing a comprehensive multi -physics model of the Moroccan TRIGA Mark II.