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So far, only individual absorbing materials have been studied for neutron absorption in the pool-type reactor spent fuel storages. In this paper, the effect of combining various materials, which are already known as good neutron absorbers by themselves, on lowering the multiplication factor of spent fuel pool, is described. The results of Monte Carlo computer code MCNP calculations for the spent fuel pool of the TRIGA research reactor in Ljubljana, Slovenia, are specified. Due to property completion of the chosen absorber materials, some of their combinations partially decrease the multiplication factor and thus contribute to the enhancement of the safety conditions of the pool.

The effect of combination of different materials on neutron absorption in a nuclear research reactor spent fuel pool