MODELING AND ANALYSIS OF FLUX AND POWER DISTRIBUTION FOR HTR-10 REACTOR CORE

Résumé

MCNP6 computer code is used to model HTR-10 core reactor. UO2 fuel is used. We predict the Flux and power distribution for normal core loaded by UO2 fuel pebbles of the reference HTR-10 reactor. The MCNP model consisted of the reactor structure which included the graphite reflector, the borated carbon bricks surrounding it and the pebble-bed core. The results show an analogue between the thermal neutron flux distribution and the power distribution, where the thermal neutrons are responsible for causing the fission, and hence power generation. The thermal neutron flux and power generation have its maximum value at the core center and decreases as we move away from the center to core boundary. The thermal flux is increased near the reflector because the neutron reflector scatters back (or reflects) into the core many neutrons that would otherwise escape. The neutrons reflected back into the core are available for chain reaction (reflector savings).

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