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Criticality analysis of pyrochemical reprocessing apparatuses for mixed uranium-plutonium nitride spent nuclear fuel using the MCU-FR and MCNP program codes

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초록

A preliminary criticality analysis for novel pyrochemical apparatuses for the reprocessing of mixed uranium-plutonium nitride spent nuclear fuel from the BREST-OD-300 reactor was performed. Hightemperature processing apparatuses, “metallization” electrolyzer, refinery remelting apparatus, refining electrolyzer, and “soft” chlorination apparatus are considered in this work. Computational models of apparatuses for two neutron radiation transport codes (MCU-FR and MCNP) were developed and calculations for criticality were completed using the Monte Carlo method. The criticality analysis was performed for different loads of fissile material into the apparatuses including overloading conditions. Various emergency situations were considered, in particular, those associated with water ingress into the chamber of the refinery remelting apparatus. It was revealed that for all the considered computational models nuclear safety rules are satisfied.

Abstract

A preliminary criticality analysis for novel pyrochemical apparatuses for the reprocessing of mixed uranium-plutonium nitride spent nuclear fuel from the BREST-OD-300 reactor was performed. Hightemperature processing apparatuses, “metallization” electrolyzer, refinery remelting apparatus, refining electrolyzer, and “soft” chlorination apparatus are considered in this work. Computational models of apparatuses for two neutron radiation transport codes (MCU-FR and MCNP) were developed and calculations for criticality were completed using the Monte Carlo method. The criticality analysis was performed for different loads of fissile material into the apparatuses including overloading conditions. Various emergency situations were considered, in particular, those associated with water ingress into the chamber of the refinery remelting apparatus. It was revealed that for all the considered computational models nuclear safety rules are satisfied.

참고문헌 (25)

  1. Nuclear Technology Review 2020, , International Atomic Energy Agency, 1~67, pp.GC(64) (2020), INF[DOI]
  2. R. G. Lewin, "Reprocessing and Recycling of Spent Nuclear Fuel", pp.373~413 (2015), Woodhead Publishing
  3. A. Salyulev, "The electrical conductivity of model melts based on LiCl-KCl, used for the processing of spent nuclear fuel", J. Electrochim. Acta, 257, pp.510~515 (2017)
  4. Alexander Zhitkov, "Interaction between UN and CdCl2 in molten LiCl-KCl eutectic. I. Experiment at 773 K", Nuclear Engineering and Technology, 52(1), pp.123~134 (2020), 한국원자력학회
  5. Alexander Salyulev, "Electrical Conductivity of (LiCl–KCl)<sub>eut.<", sub>–SrCl<sub>2<, Journal of Chemical &amp; Engineering Data, pp.2021, 66(12)[DOI]
  6. A. B. Salyulev, "Distillation of Lithium Chloride From the Products of Uranium Dioxide Metalization", Atomic Energy, 126(4), pp.226~229 (2019), Springer Science and Business Media LLC[DOI]
  7. Yu P Zaikov, "Research and Development of the pyrochemical processing for the mixed nitride uranium-plutonium fuel", Journal of Physics: Conference Series, 1475(1), pp.012027~ (2020), IOP Publishing[DOI]
  8. E. O. Adamov, "Spent nuclear fuel reprocessing and nuclear materials recycling in two-component nuclear energy", J. At. Energy, 130(1), pp.29~35 (2021)[DOI]
  9. A A Zherebtsov, "Development of the general design of the industrial energy complex with CNFC", Journal of Physics: Conference Series, 1475(1), pp.012007~ (2020), IOP Publishing[DOI]
  10. J. J. Laidler, "Development of pyroprocessing technology", J. Prog. Nucl. Energy, 31(1), pp.131~140 (1997)
  11. Developments of Spent Nuclear Fuel Pyroprocessing Technology at Idaho National Laboratory, "M.F. Simpson", Idaho National Laboratory, 1~21, pp.INL (2012), EXT-12-25124
  12. J. -G. Kim, "High-throughput electrorefining system with graphite cathodes and a bucket-type deposit retriever", J. Procedia Chem, 7, pp.754~757 (2012)
  13. F. GAO, "Criticality safety evaluation of materials concerning pyroprocessing", J. Nucl. Sci. Technol, 48(6), pp.919~928 (2011)
  14. T. Inoue, "State of the art of pyroprocessing technology in Japan", J. Energy Procedia, 7, pp.405~413 (2011)
  15. K. Nagarajan, "Development of pyrochemical reprocessing for spent metal fuels", J. Energy Procedia, 7, pp.431~436 (2011)
  16. E. Mendes, "Application of the pyrochemical DOS, developed by the CEA, within reprocessing of CERCER transmutation fuel targets", J. Procedia Chem, 21, pp.433~440 (2016)
  17. Federal (Russian) Rules and Regulations in the Field of Nuclear Energy Use Nuclear Fuel Cycle Facilities, Federal Environmental, , Industrial and Nuclear Supervision Service, 1~37, pp.NP-063-05 (2005)
  18. M. A. Kalugin, "Overview of the MCU Monte Carlo software package", J. Ann. Nucl. Energy, 82, pp.54~62 (2015)
  19. MCNP ― A General Monte Carlo N-Particle Transport Code, Version 5, "X-5 Monte Carlo Team", Los Alamos National Laboratory, 1~416, pp.LA-UR-03-1987 (2008)
  20. N. I. Alekseev, "The status of MCU-5", J. Phys. At. Nuclei, 75(14), pp.1634~1646 (2012)
  21. A. Plompen, "The joint evaluated fission and fusion nuclear data library, JEFF-3.3", J. Eur. Phys. J. A, 56, pp.181~ (2020)
  22. S.V. Zabrodskaya, "ROSFOND ― Russian national library of neutron data", Ser. Nucl. constants, 1 - 2, pp.3~21 (2007)
  23. A. G. Glazov, "Brest reactor and plant-site nuclear fuel cycle", J. At. Energy, 103(1), pp.501~508 (2007)
  24. Fission Neutron Source in Monte Carlo Calculations for Loosely Coupled Systems, "P.A. Kizub", Nuclear Safety Institute of the Russian Academy of Sciences, 1~30, pp.IBRAE-2015-02 (2015)
  25. E. F. Mitenkova, "Distribution of the fission reaction rate in a loosely coupled system for the"checkerboard"test model", J. At. Energy, 116(6), pp.345~349 (2014)

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