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Radiation Conditions During the Fabrication of Experimental Fuel Elements from Reprocessed Fuel

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Abstract

The results of an investigation of the safety of the fabrication of experimental fuel elements with a vibrationally compacted kernels consisting of reprocessed mixed fuel are presented. Data indicating the interrelationship of the granulometric composition of the product used in the technology and the intensity of the generation of the dispersion-distributed aerosol particles are presented. The postoperation structure of the surface contamination of the equipment in the setup used for fabricating fuel elements is studied. An expression is obtained for estimating the expected flow of radioactive substances into the exhaust systems of the ventillation center. The absolute values of the flow of radioactive aerosols into the environment are determined. The results of measurements of the exposure dose rate of an experimental fuel element and data on the material balance of the fuel composition and its main components are presented. The irradiation of workers participating at all stages of the process is estimated.

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REFERENCES

  1. V. V. Serebryakov, A. P. Kirillovich, A. F. Sviridov, et al., “Investigation of 85Kr yield and the influence of 85Kr on the radiation conditions during preparation of BOR-60 fuel for reprocessing,” At. Energ., 94, No.3, 220–226 (2003).

    Google Scholar 

  2. V. V. Serebryakov, A. P. Kirillovich, and I. Yu. Zhemkov, “Radiation conditions during preparation of irradiated BOR-60 fuel assemblies for reprocessing,” At. Energ., 95, No.2, 140–147 (2003).

    Google Scholar 

  3. V. V. Serebryakov, A. P. Kirillovich, A. V. Bychkov, et al., “Safety of repocessing spent BOR-60 fuel by the pyro-electrochemical method,” At. Energ., 98, No.4, 280–288 (2005).

    Google Scholar 

  4. A. P. Kirillovich, A. V. Bychkov, A. A. Maershin, et al., “Radiation-ecological aspects of a closed fuel cycle for a BOR-60 reactor,” in: International Conference on Nuclear Power and Fuel Cycles, Moscow-Dimitrovgrad (2003), NIKIET, Moscow (2003), pp. 47–48.

  5. A. V. Bychko, “Future development of water-free processes for reprocessing spent nuclear fuel and the method of vibrational compaction,” ibid., pp. 37–38.

  6. V. B. Mishenev, V. V. Tikhomirov, A. N. Zhdanov, et al., “Analytical support for the system for taking account and monitoring nuclear materials at the State Science Center of the Russian Federation Scientific-Research Institute of Nuclear Reactors,” in: Estimation of the Content and Available Quantities of Nuclear Materials in Circulation and in Wastes, Physics and Power-Engineering Institute, Obninsk (2003), pp. 161–165.

    Google Scholar 

  7. I. V. Petryanov, V. I. Kozlov, P. I. Basmanov, et al., Fibrous Filtering Materials FT, Znanie, Moscow (1968).

    Google Scholar 

  8. N. B. Borisov, P. I. Basmanov, and L. I. Borisova, “AFA analytical filters for studying aerosols,” in: 3rd Petryanov Lectures, RITs MGIU, Moscow (2001), pp. 229–266.

    Google Scholar 

  9. A. V. Nazarov, A. V. Narashchenko, and V. Yu. Usol’tsev, “Mathematical simulation of continuous binomial distribution for analysing randomly distributed quantities,” in: New Technologies for Power Engineering, Industry, and Construction, NIIAR, Dimitrovgrad (2000), No. 2, pp. 286–189 [sic].

    Google Scholar 

  10. A. P. Kirillovich, O. A. Kochetkov, Yu. G. Lavrinovich, et al., “Radiation conditions on the experimental-research complex of the Scientific-Research Institute of Nuclear Reactors for production of granular fuel and fabrication of fuel elements and fuel assemblies for fast-neutron reactors,” Preprint NIIAR-4(343) (1994).

  11. A. P. Kirillovich, “Methodology and analysis of production safety during recycling of plutonium at the State Science Center Scientific-Research Institute of Nuclear Reactors,” At. Energ., 87, No.4, 266–275 (1999).

    Google Scholar 

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Authors and Affiliations

  1. Scientific-Research Institute of Nuclear Reactors, Russia

    V. V. Serebryakov, A. P. Kirillovich, A. A. Maershin, O. V. Shishalov & A. V. Orishchenko

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  1. V. V. Serebryakov
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  2. A. P. Kirillovich
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  3. A. A. Maershin
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  4. O. V. Shishalov
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  5. A. V. Orishchenko
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__________

Translated from Atomnaya Energiya, Vol. 98, No. 5, pp. 351–360, May 2005.

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Serebryakov, V.V., Kirillovich, A.P., Maershin, A.A. et al. Radiation Conditions During the Fabrication of Experimental Fuel Elements from Reprocessed Fuel. At Energy 98, 334–342 (2005). https://doi.org/10.1007/s10512-005-0214-6

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  • DOI: https://doi.org/10.1007/s10512-005-0214-6

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