The radioactive activity of spent nuclear fuel is high, and the transportation safety is concerned by public and specialist. The periodic radiation shielding performance measurements of spent fuels package is important content to ensure transportation safety of spent fuels. The radiation shielding performance of package must meet the requirements of “Regulations for the safe transport of radioactive material” (GB11806-2004). However, some of the problems and difficulties reflected in practice need to be solved, such as the measurements results of neutron radiation level of spent fuels package outer are not always reliable. In this paper, the periodic shielding performance measurements of one type of spent fuel transportation package are presented. The monitoring results of using both the neutron multi-sphere spectrometer and portable neutron measurement instrument are compared, and the Monte Carlo simulation is done to verify the measurements results. Some factors are discussed, and an optimized scheme is recommended.
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2017 25th International Conference on Nuclear Engineering
July 2–6, 2017
Shanghai, China
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5785-4
PROCEEDINGS PAPER
Study on Periodic Shielding Performance Measurements of Spent Fuel Transportation Package
Hongchao Sun,
Hongchao Sun
China Institute for Radiation Protection, Taiyuan, China
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Guoqiang Li,
Guoqiang Li
China Institute for Radiation Protection, Taiyuan, China
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Xuexin Wang,
Xuexin Wang
China Institute for Radiation Protection, Taiyuan, China
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Dajie Zhuang,
Dajie Zhuang
China Institute for Radiation Protection, Taiyuan, China
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Renze Wang,
Renze Wang
China Institute for Radiation Protection, Taiyuan, China
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Shutang Sun,
Shutang Sun
China Institute for Radiation Protection, Taiyuan, China
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Meng Dongyuan
Meng Dongyuan
China Institute for Radiation Protection, Taiyuan, China
Search for other works by this author on:
Hongchao Sun
China Institute for Radiation Protection, Taiyuan, China
Guoqiang Li
China Institute for Radiation Protection, Taiyuan, China
Xuexin Wang
China Institute for Radiation Protection, Taiyuan, China
Dajie Zhuang
China Institute for Radiation Protection, Taiyuan, China
Renze Wang
China Institute for Radiation Protection, Taiyuan, China
Shutang Sun
China Institute for Radiation Protection, Taiyuan, China
Meng Dongyuan
China Institute for Radiation Protection, Taiyuan, China
Paper No:
ICONE25-66036, V007T10A001; 4 pages
Published Online:
October 17, 2017
Citation
Sun, H, Li, G, Wang, X, Zhuang, D, Wang, R, Sun, S, & Dongyuan, M. "Study on Periodic Shielding Performance Measurements of Spent Fuel Transportation Package." Proceedings of the 2017 25th International Conference on Nuclear Engineering. Volume 7: Fuel Cycle, Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Mitigation Strategies for Beyond Design Basis Events. Shanghai, China. July 2–6, 2017. V007T10A001. ASME. https://doi.org/10.1115/ICONE25-66036
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