Abstract: In the event of nuclear accidents or emergency, high radiation in the reactor will do great harm to human health. Currently, domestic radiation protection products are mostly targeted for the single-type radiation and aimed at low-energy radiation, which can not meet the needs of nuclear emergency operations. In this work, a kind of neutron/γ radiation protection material was designed based on the Monte Carlo particle transport program. The thickness and shielding performance were studied, and the shielding performance simulated by Monte Carlo was verified by experimental tests. The results show that thickness of 5 mm can meet the requirements of radiation shielding. The simulated shielding rates of medium energy γ-rays and slow neutrons are 21.42% and 78.79%, while the experimental values are 20.61% and 88.2% respectively. The simulation results are in good agreement with the experimental results, indicating that the Monte Carlo method had good guiding significance for radiation protection material design.
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2022, Vol. 36 
