The structure of the public radiation dose resulting from gas aerosol emissions of the experimental-demonstration energy complex incorporating the BREST-OD-300 reactor and fuel fabrication and reprocessing modules is determined. The yearly radiation dose to humans at the point of maximum ground concentration of radionuclides from design basis emissions of the energy complex is formed primarily by 3H,14C, and fission products (0.73, 1.2 2, and 0.9 μSv, respectively) through the peroral pathway as a result of the fallout during the running year of operation of the enterprises. The largest contribution to the irradiation dose is due to the emissions from the spent fuel reprocessing module – 2.33 μSv/yr – and 50% is due to 14C. The radiation dose from the emissions of the BREST-OD-300 reactor is almost completely due to 3H and 210Po (0.73 and 0.17 μSv/yr, respectively). The emissions from the fuel fabrication module have the smallest effect on the public. The dose from fission products is produced by emissions from the reprocessing module approximately in equal amounts in terms of external and internal pathways (0.47 and 0.43 μSv).
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Translated from Atomnaya Energiya, Vo. 124, No. 3, pp. 169–173, March, 2018.
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Spirin, E.V., Aleksakhin, R.M. & Bazhanov, A.A. Structure of the Public Irradiation Dose During Operation of Experimental-Demonstration Power Complex Enterprises. At Energy 124, 203–209 (2018). https://doi.org/10.1007/s10512-018-0398-1
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DOI: https://doi.org/10.1007/s10512-018-0398-1