In this paper, NAC-STC (spent fuel transport cask) package operation is studied. The calculated / measured doses of different parts of the cask surface (or 1 m and 2 m away) in the course of package operation are analyzed. The radiation risk control methods are proposed to protect the operators exposed in the high dose area.
- Nuclear Engineering Division
Dose Distribution in the Spent Fuel Package Operations and the Radiation Risk Control
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Lü, G, Wei, M, Zhang, Z, Li, S, & Han, X. "Dose Distribution in the Spent Fuel Package Operations and the Radiation Risk Control." Proceedings of the 2013 21st International Conference on Nuclear Engineering. Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Radiation Protection and Nuclear Technology Applications. Chengdu, China. July 29–August 2, 2013. V001T04A034. ASME. https://doi.org/10.1115/ICONE21-16854
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