Optimization of radiation shields made of Fe and Pb for the spent nuclear fuel transport casks

Abstract

Recommendations are given to improve the efficiency of radiation protection of transport casks for SNF transportation. The attenuation of γ-quanta of long-lived isotopes 134Cs, 137mBa(137Cs), 154Eu and 60Co by optimizing the thicknesses and arrangement of layers of Fe and Pb radiation shields of transport casks is studied. The fixed radiation shielding mass (fixed mass thickness) is chosen as the main optimization criterion. The effect of the placement order of Fe and Pb layers in a combined two-layer radiation shield with an equivalent thickness of 30 cm is studied in detail. It is shown that with the same mass thicknesses of the Fe and Pb layers, the placement of Fe in the first layer, and Pb - in the second one provides more than twofold attenuation of γ-quanta compared to the reverse placement: Pb - in the first layer, Fe - in the second. The increase in the efficiency of attenuation of γ-quanta for TC with combined shielding of Fe and Pb is shown to be achieved by designing the first layer of radiation shielding around the canister with SNF from Fe of the maximum possible thickness.

Keywords

• Spent nuclear fuel
• Radiation shield
• Dry cask storage
• Multilayer shield''