Radiation Safety Analysis for Dry Storage of Spent Fuel Elements

XIE Siyang; DU Ying; CHEN Zonghuan; XU Cong; GAO Guiling; ZHOU Guanglai; ZHOU Chenglong; YAO Lin

doi:10.19554/j.cnki.1001-3563.2026.13.006

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Packaging Engineering ›› 2026, Vol. 47 ›› Issue (13) : 46-51. DOI: 10.19554/j.cnki.1001-3563.2026.13.006

Special Topic on Radiation Protection and Shielding Technologies for Multiple Scenarios in Complex Radiation Fields

Radiation Safety Analysis for Dry Storage of Spent Fuel Elements

XIE Siyang¹, DU Ying¹, CHEN Zonghuan¹, XU Cong¹, GAO Guiling¹, ZHOU Guanglai², ZHOU Chenglong³, YAO Lin^1*

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Abstract

The work aims to analyze the radiation safety of dry storage facilities of spent fuel elements under different working conditions based on the source term characteristics of spent fuel elements in the high-temperature gas-cooled reactor (HTGR), to make them meet relevant requirements of GB 11806-2019 and GB 18871-2002. The photon energy spectrum of spherical spent fuel elements in the HTGR was determined in combination with the radioactive levels of each nuclide. Monte Carlo codes were used to establish three-dimensional refined shielding models for ventilation ducts and shielding plug gaps within transport casks and dry storage facilities. Radiation safety analyses were conducted for two typical scenarios: spent fuel transport and storage. The results indicated that the maximum dose rate on the surface of the transport cask was 1.42 mSv/h, and the maximum dose rate at the shielding plug gap of the storage well utilizing a two-stage step structure was 3.99 μSv/h. Furthermore, the annual effective dose for workers was 7.98 mSv. All parameters complied with the dose limit requirements specified in relevant standards. This study verifies the reliability of the radiation safety design for the HTGR spent fuel dry storage scheme and provides critical data support for the engineering design of similar facilities.

Key words

spent fuel elements / dry storage / radiation safety

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XIE Siyang, DU Ying, CHEN Zonghuan, XU Cong, GAO Guiling, ZHOU Guanglai, ZHOU Chenglong, YAO Lin. Radiation Safety Analysis for Dry Storage of Spent Fuel Elements[J]. Packaging Engineering. 2026, 47(13): 46-51 https://doi.org/10.19554/j.cnki.1001-3563.2026.13.006

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