In this master's thesis, I analysed the core of a multifunctional microreactor. The aim was to design a core that would be adaptable and could serve different purposes by swapping some of the fuel assemblies. UZrH fuel was selected because part of the moderator is present directly in the fuel, leading to a prompt temperature feedback effect. The analysis covered determining acceptable parameters for the fuel pin, assembly and core geometry, favourable short-term control methods, as well as irradiation channel positions and neutron spectrum properties.
The simulations were performed using the open-source stochastic programme for neutron and photon transport, OpenMC. The parametric study demonstrated that the primary core design is undermoderated and the reactivity feedback coefficients are negative. Control rods were chosen for reactivity control, as they provided sufficient negative reactivity to safely shut down the reactor, while also being spatially convenient. The OpenMC model was later coupled with internal programmes for thermohydraulic calculations. The core was optimised by using different fuel enrichments in the fuel assemblies and by adding burnable absorber coatings to some of the fuel pins. With this configuration, the power peaking factors were calculated to be within the limits known for functioning reactors. Using these enrichments and burnable absorber positions, core configurations with irradiation channels were simulated, and their power peaking factors calculated.
The results indicate that the considered microreactor can operate with parameters within the safety limitations, with the power peaking factors being the main non-trivial challenge. In further analysis the control rods were separated into banks for better control and a more even neutron flux distribution. Finally, different neutron spectra can be achieved by using specific materials in the irradiation channel, enabling the irradiation conditions to be tailored to the requirements of specific applications and consequently enhancing the efficiency of neutron activation, materials characterization, and other neutron-based experiments.
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