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Article

  • Title

    DEVELOPMENT OF A THREE-DIMENSIONAL MODEL OF THE VVER-1000 REACTOR USING SERPENT MONTE CARLO CODE FOR NEUTRON-PHYSICAL MODELING

  • Authors

    Gulik V.
    Galchenko V.
    Shlapak I.
    Budik D.

  • Subject

    ENERGETICS. HEAT ENGINEERING. ELECTRICAL ENGINEERING

  • Year 2020
    Issue 1(60)
    UDC 621.039.51
    DOI 10.15276/opu.1.60.2020.05
    Pages 47-52
  • Abstract

    The VVER reactor investigation is an important goal for Ukrainian nuclear energy. Different deterministic and stochastic codes are using for this purpose. With taking into account the fast development of computer systems, there is a possibility for active using stochastic codes (based on Monte-Carlo method) for simulation of complicated reactor systems. The investigation for implementation of Monte-Carlo code to calculate whole reactor VVER-1000 core was presented in this article. Such type of calculations would be a base for preparation of “information support data” with high accuracy deterministic code for in core monitoring system. The “information support data” includes group constants, coefficients for calculations of model currents, albedo boundary conditions for radial and axial reflectors. The paper presents the use of the new Monte-Carlo Serpent code for the three-dimensional modelling of the VVER-1000 reactor core. The use of Monte-Carlo codes offers an opportunity to analyze the properties of a wide range of the neutron-physical and thermal-hydraulic characteristics at any reactor point. In the work, core models were developed for the Rivne NPP4 first loading and the South-Ukraine NPP3 28th loading. At the same time, assembly models of various manufacturers were prepared. During the core model developing, considerable attention was paid to the upper, lower and side reflectors for detailed modelling. The Monte-Carlo Serpent code validation calculations for the VVER-1000 reactor were performed based on the Rivne NPP4 first loading. The albedo boundary conditions for radial and axial reflectors were obtained for the South-Ukraine NPP3 28th loading. The prepared VVER-1000 reactor core models will use for “information support data” calculations for new Ukrainian In-core monitoring system deterministic code – ImCore, which is under development at PJSC “SRPA “Impulse”. Using computer code based on Monte-Carlo method will provide an opportunity for increasing accuracy of “information support data” and as a consequence, increase the accuracy for VVER-1000 reactor calculations in In-core monitoring system.

  • Keywords nuclear reactor, VVER-1000, calculation of nuclear reactor, Monte Carlo method, core modeling
  • Viewed: 270 Dowloaded: 8
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  • References

    Література

    1. Modeling and control of nuclear reactor cores for electricity generation: A review of advanced technologies / Li G., Wang X., Liang B., Li X., et al. Renewable and Sustainable Energy Reviews. 2016. Vol. 60. P. 116–128.

    2. The reactor dynamics code DYN3D – models, validation and applications / Rohde U., Kliem S., Grundmann U., et al. Progress in Nuclear Energy. 2016. Vol. 89. P. 170–190.

    3. Current status of the reactor physics code WIMS and recent developments / Lindley B.A., Hosking J.G., Smith P.J., et al. Annals of Nuclear Energy. 2017. Vol. 102. P. 148–157.

    4. Galchenko V.V., Gulik V.I., Shlapak I.I. Using of the Serpent code based on the Monte-Carlo method for calculation of the VVER-1000 fuel assembly characteristics. Nuclear Physics and Atomic Energy. 2016. Vol. 17(3). P. 250–258.

    5. Leppдnen J., Pusa M., Fridman E. Overview of methodology for spatial homogenization in the Serpent 2 Monte Carlo code. Annals of Nuclear Energy. 2016. Vol. 96. P. 126–136.

    6. The Serpent Monte Carlo code: Status, development and applications in 2013 / Leppдnen J., Pusa M., Viitanen T., et al. Annals of Nuclear Energy. 2015. Vol. 82. P. 142–150.

    7. Velocity Characteristic and Stability of Wave Solutions for a CANDLE Reactor with Thermal Feedback / Khotyayintsev V.M., Aksonov A.V., Khotyayintseva O.M., et al. Annals of Nuclear Energy. 2015. Vol. 85. P. 337–345.

    8. Galchenko V.V., Shlapak I.I., Gulik V.I. The computational benchmark for fuel assembly of VVER- 1000 with using Monte Carlo Serpent code. Nuclear Technology & Radiation Protection. 2018. Vol. 33(1). P. 24–30.

    9. Radiation shielding properties of a novel cement-basalt mixture for nuclear energy applications / Ipbьker C., Nulk H., Gulik V., et al. Nuclear Engineering and Design. 2015. Vol. 284. P. 27–37.

    References

    1. Li, G., Wang, X., Liang, B., & Li, X., et al. (2016). Modeling and control of nuclear reactor cores for electricity generation: A review of advanced technologies. Renewable and Sustainable Energy Reviews,60, 116–128.

    2. Rohde, U., Kliem, S., & Grundmann, U., et al. (2016). The reactor dynamics code DYN3D – models, validation and applications. Progress in Nuclear Energy, 89, 170–190.

    3. Lindley, B.A., Hosking, J.G., & Smith, P.J., et al. (2017). Current status of the reactor physics code WIMS and recent developments. Annals of Nuclear Energy, 102, 148–157.

    4. Galchenko, V.V., Gulik, V.I., & Shlapak, I.I. (2016). Using of the Serpent code based on the Monte- Carlo method for calculation of the VVER-1000 fuel assembly characteristics. Nuclear Physics and Atomic Energy, 17(3), 250–258.

    5. Leppдnen, J., Pusa, M., & Fridman, E. (2016). Overview of methodology for spatial homogenization in the Serpent 2 Monte Carlo code. Annals of Nuclear Energy, 96, 126–136.

    6. Leppдnen, J., Pusa, M., & Viitanen, T., et al. (2015). The Serpent Monte Carlo code: Status, development and applications in 2013. Annals of Nuclear Energy, 82, 142–150.

    7. Khotyayintsev, V.M., Aksonov, A.V., & Khotyayintseva, O.M., et al. (2015). Velocity Characteristic and Stability of Wave Solutions for a CANDLE Reactor with Thermal Feedback. Annals of Nuclear Energy, 85, 337–345.

    8. Galchenko, V.V., Shlapak, I.I., & Gulik, V.I. (2018). The computational benchmark for fuel assembly of VVER-1000 with using Monte Carlo Serpent code. Nuclear Technology & Radiation Protection, 33(1), 24–30.

    9. Ipbьker, C., Nulk, H., & Gulik, V., et al. (2015). Radiation shielding properties of a novel cement-basalt mixture for nuclear energy applications. Nuclear Engineering and Design, 284, 27–37.

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