Shielding Research on CNSC-24S Spent Fuel Transport Cask

CHEN Zonghuan; ZHANG Ye; WU Peng; XIE Siyang; YAO Lin; WANG Bingheng

doi:10.19554/j.cnki.1001-3563.2026.15.032

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Packaging Engineering ›› 2026, Vol. 47 ›› Issue (15) : 319-325. DOI: 10.19554/j.cnki.1001-3563.2026.15.032

Equipment Protection

Shielding Research on CNSC-24S Spent Fuel Transport Cask

CHEN Zonghuan¹, ZHANG Ye¹, WU Peng², XIE Siyang¹, YAO Lin^1,*, WANG Bingheng¹

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Abstract

The work aims to study the shielding performance optimization of CNSC-24S spent fuel transport casks to overcome the insufficient loading capacity, decay heat limits of existing spent fuel transport casks and meet the transportation requirements for high-burnup, short-cooling-time spent fuel assemblies from domestic nuclear power plants. Based on GB 11806-2019 "Regulations for the Safe Transport of Radioactive Material", the latest ICRP 116 flux-to-dose conversion coefficients were employed to establish Monte Carlo shielding analysis models for both 24-assembly and 20-assembly loading configurations. By comparing the differences between ICRP 74 and ICRP 116 flux-to-dose coefficients, and incorporating the arrangement of heat-conducting shields and compensatory shielding design at the upper basket, dose rate assessments were conducted for various external positions of the cask under normal transportation conditions. When calculated using ICRP 116 coefficients, the maximum surface dose rate of the cask decreased from 2.45 mSv/h to 1.67 mSv/h, and the dose rate at 2 m from the vehicle exterior decreased from 0.126 mSv/h to 0.087 5 mSv/h, meeting national standards. The 20-assembly loading scheme, combined with heat-conducting shields, enabled safe transportation of spent fuel assemblies with individual decay heat of 1.2 kW and cooling time of 7.4 years. The compensatory shielding at the trunnion area reduced the local dose rate from 2.12 mSv/h to 1.33 mSv/h, eliminating the risk of excessive radiation exposure for operators. Through optimization of flux-to-dose conversion coefficient selection, loading configurations, and local shielding structures, the CNSC-24S cask achieves safe transportation of spent fuel with a maximum capacity of 24 assemblies and total decay heat of 24 kW. All radiation indicators satisfy relevant requirements of GB 11806-2019, effectively enhancing the technical capability and market competitiveness of domestically produced spent fuel transport casks.

Key words

spent fuel transport cask / shielding design / flux-to-dose conversion coefficient

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CHEN Zonghuan, ZHANG Ye, WU Peng, XIE Siyang, YAO Lin, WANG Bingheng. Shielding Research on CNSC-24S Spent Fuel Transport Cask[J]. Packaging Engineering. 2026, 47(15): 319-325 https://doi.org/10.19554/j.cnki.1001-3563.2026.15.032

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