Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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Radioactive gas diffusion simulation and inhaled effective dose evaluation during nuclear decommissioning

  • Yang, Li-qun (Fundamental Science on Nuclear Safety and Simulation Technology Laboratory, Harbin Engineering University) ;
  • Liu, Yong-kuo (Fundamental Science on Nuclear Safety and Simulation Technology Laboratory, Harbin Engineering University) ;
  • Peng, Min-jun (Fundamental Science on Nuclear Safety and Simulation Technology Laboratory, Harbin Engineering University) ;
  • Ayodeji, Abiodun (Fundamental Science on Nuclear Safety and Simulation Technology Laboratory, Harbin Engineering University) ;
  • Chen, Zhi-tao (Fundamental Science on Nuclear Safety and Simulation Technology Laboratory, Harbin Engineering University) ;
  • Long, Ze-yu (Fundamental Science on Nuclear Safety and Simulation Technology Laboratory, Harbin Engineering University)
  • Received : 2021.01.15
  • Accepted : 2021.07.13
  • Published : 2022.01.25
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Abstract

During the decommissioning of the nuclear facilities, the radioactive gases in pressure vessels may leak due to the demolition operations. The decommissioning site has large space, slow air circulation, and many large nuclear facilities, which increase the difficulty of workers' inhalation exposure assessment. In order to dynamically evaluate the activity distribution of radionuclides and the committed effective dose from inhalation in nuclear decommissioning environment, an inhalation exposure assessment method based on the modified eddy-diffusion model and the inhaled dose conversion factor is proposed in this paper. The method takes into account the influence of building, facilities, exhaust ducts, etc. on the distribution of radioactive gases, and can evaluate the influence of radioactive gases diffusion on workers during the decommissioning of nuclear facilities.

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Acknowledgement

This research work was funded by Fundamental Science on Nuclear Safety and Simulation Technology Laboratory, Harbin Engineering University, Decommissioning of Nuclear Facilities and Radioactive Waste Management Research, Project supported by the Natural Science Foundation of Heilongjiang Province, China (Grant NO. A2016002), the technical support project for Suzhou Nuclear Power Research Institute(SNPI) (NO.029-GN-B-2018-C45-P.0.99-00003), the Foundation of Science and Technology on Reactor System Design Technology Laboratory (HT-KFKT-14-2017003) and the project of Research Institute of Nuclear Power Operation (No.RIN180149-SCCG).

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