Nuclear Engineering and Technology

  • 제54권1호
  • /
  • Pages.293-300
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  • 2022
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  • 1738-5733(pISSN)
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  • 2234-358X(eISSN)
한국원자력학회 (Korean Nuclear Society)
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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)
  • 투고 : 2021.01.15
  • 심사 : 2021.07.13
  • 발행 : 2022.01.25
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초록

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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과제정보

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).

참고문헌

  1. C. Keil, R. Murphy, An application of exposure modeling in exposure assessments for a university chemistry teaching laboratory, J. Occup. Environ. Hyg. 3 (2) (2006) 99-106. https://doi.org/10.1080/15459620500498109
  2. J. Spencer, M. Plisko, A comparison study using a mathematical model and actual exposure monitoring for estimating solvent exposures during the disassembly of metal parts, J. Occup. Environ. Hyg. 4 (4) (2007) 7.
  3. E. Demou, S. Hellweg, M.P. Wilson, S.K. Hammond, T.E. Mckone, Evaluating indoor exposure modeling alternatives for lca: a case study in the vehicle repair industry, Environ. Sci. Technol. 43 (15) (2009) 5804-5810. https://doi.org/10.1021/es803551y
  4. P.J. Drivas, P.A. Valberg, B.L. Murphy, R. Wilson, Modeling indoor air exposure from short-term point source releases, Indoor Air 6 (4) (1996) 271-277. https://doi.org/10.1111/j.1600-0668.1996.00006.x
  5. P.A. Scheff, J.E. Franke, R.A. Wadden, Emission factors for trichloroethylene vapor degreasers, American Indsutrial Hygiene Association 50 (9) (1989) 496-500. https://doi.org/10.1080/15298668991375047
  6. C. Keil, Mathematical Models for Estimating Occupational Exposure to Chemicals, American Indsutrial Hygiene Association, 2000.
  7. B.C. Keil, A tiered approach to deterministic models for indoor air exposures, Appl. Occup. Environ. Hyg 15 (1) (2000) 145-151. https://doi.org/10.1080/104732200301962
  8. L.Q. Yang, Y.K. Liu, M.J. Peng, M.K. Li, A gamma-ray dose rate assessment method for arbitrary shape geometries based on voxelization algorithm, Radiat. Phys. Chem. 158 (2019) 122-130. https://doi.org/10.1016/j.radphyschem.2019.02.015
  9. G. Wang, W. Lu, S. Liang, H. Kuang, D. Chen, J. Luo, T. Yu, Adoption of lung absorption type for radionuclides based upon a national standard, Radiat. Protect. 33 (4) (2013) 253-256.