Ваш браузер устарел.

Для того, чтобы использовать все возможности сайта, загрузите и установите один из этих браузеров.

скрыть

Article

  • Title

    QUALIFICATION OF AFTERHEAT REMOVAL PASSIVE SYSTEM FROM REACTOR TO MANAGE BLACKOUT ACCIDENTS

  • Authors

    Skalozubov Volodymyr
    Spinov Vladislav
    Gabalaya Taisiya
    Kochnyeva Valeria
    Skalozubov Kostyantin

  • Subject

    ENERGETICS. HEAT ENGINEERING. ELECTRICAL ENGINEERING

  • Year 2019
    Issue 3(59)
    UDC 629.031
    DOI 10.15276/opu.3.59.2019.03
    Pages 19-24
  • Abstract

    Nuclear safety criteria and conditions for the maximum admissible temperatures of nuclear fuel and fuel claddings, for the pressure and coolant flow of the steam-driven emergency pump and for dimensions of using natural circulation are qualification criteria and conditions for operability and reliability of the presented afterheat removal passive system from the reactor to manage blackout accidents. The conservative heathydrodynamic model of qualification of afterheat removal passive system from the reactor is developed for blackout accident management. Calculation modelling with the presented conservative model has recognized that design blackout accident management strategy does not ensure nuclear safety conditions. The modernized accident management strategy with afterheat removal passive system from the reactor provides nuclear safety conditions. According to Prof. Korolev’s experiments, operability of the steam-driven emergency pump is provided when the reactor pressure is more than 0.3 MPa. For smaller pressure, the afterheat removal passive subsystem using natural circulation provides safety functions. The results of this work can be used to modernize nuclear power plants with the view of increasing the efficiency of blackout accident management, and to improve symptom-informed instructions and guidelines for the accident management of severe fuel damages. The proposed blackout accident management system can be supplemented with steam removal passive safety systems through steam generators of nuclear power plants with WWERs. The proposed passive system is effective only for blackout accidents and large loss-of-coolant accidents in the reactor (including the maximum design depressurization accident). The presented results are used for training, retraining and advanced training of specialists in Ukrainian nuclear energy.

  • Keywords qualification, passive safety system, blackout accident, reactor plant
  • Viewed: 104 Dowloaded: 2
  • Download Article
  • References

    Література

    1. Antropov V., Bukrinsky A., Shvyryaev Yu. Development of Methodology and List of BDBA for WWER-1000 for Quantitative Analysis. SAM-99 Information Exchange Forum on “Severe Accident Management”, 18 – 22 October 1999, Obninsk, Russia.

    2. Precursors to Potential Severe Core Damage Accidents: 1992. US. NRC. NUREG/CR-4674; ORNL/NOAC-232, V. 17. 1993.

    3. Analysis of nuclear safety in diversification of Westinghouse fuel assemblies at WWER-1000. / V.I. Skalozubov, I. L. Kozlov, Yu. A. Komarov, O. A. Chulkin, O. I. Piontkovskyi. Nuclear Physics and Atomic Energy. 2019. Vol. 20, issue 2. Р. 159–163. DOI: https://doi.org/10.15407/jnpae2019.02.159.

    4. Исследование поведения топлива легководных реакторов в аварийных условиях. ФГУП «ГНЦ РФ НИИАР». «ВНИИНМ». РНЦ «Курчатовский институт». 7-я конф. по реакторному материа-ловедению. Демитровград, 8-12 сентября 2003.

    5. Bibilashvili Yu.K., Sokolov N.B., Andreeva-Andrievskaya L.N. et al. Thermomechanical properties of zirconium-based alloys oxidized claddings in LOCA simulating conditions. Proc. IAEA Technical Committee Meeting «Fuel behavior under transient and LOCA conditions». (Halden, Norway, 10-14 September) 2001. P. 186–208.

    6. Расчет теплогидравлических параметров для всех режимов эксплуатации оборудования РУ энер-гоблока № 3 ОП ЗАЭС. ЕР01/2016.100.ОД.1. Т.1. 2016. 566 с.

    7. Корректировка и обновление ВАБ энергоблока № 5 ЗАЭС. EP25 – 2004.210.ОД.2 – Обесточива-ние энергоблока с отказом дизель – генераторов. Приложение G2.1. 2004. 365 c.

     

    References

     

    1. Antropov, V., Bukrinsky, A., & Shvyryaev, Yu. (1999). Development of Methodology and List of BDBA for WWER-1000 for Quantitative Analysis. SAM-99 Information Exchange Forum on “Severe Accident Management”, 18 – 22 October 1999, Obninsk, Russia.

    2. Precursors to Potential Severe Core Damage Accidents: 1992. (1993). US. NRC. NUREG/CR-4674; ORNL/NOAC-232, V. 17.

    3. Skalozubov, V.I., Kozlov, I.L., Komarov, Yu.A., Chulkin, & O.A., Piontkovskyi O.I. (2019). Analysis of nuclear safety in diversification of Westinghouse fuel assemblies at WWER-1000. Nuclear Physics and Atomic Energy, 20, 2, 159–163. DOI: https://doi.org/10.15407/jnpae2019.02.159.

    4. Investigation of the behavior of fuel of light-water reactors in emergency conditions. (2003). FSUE “SSC RU RIIAR”. “VNIINM”. RRC “Kurchatov Institute”. 7th Conference. on reactor materials sci-ence. Demitrovgrad, September 8-12.

    5. Bibilashvili, Yu.K., Sokolov, N.B., & Andreeva-Andrievskaya, L.N. et al. (2001). Thermomechanical properties of zirconium-based alloys oxidized claddings in LOCA simulating conditions. Proc. IAEA Technical Committee Meeting «Fuel behavior under transient and LOCA conditions». Halden (Nor-way), 10-14 September 2001. 186–208.

    6. Calculation of thermohydraulic parameters for all operating modes of the equipment of the Reactor of power unit No. 3 of ZNPP. (2016). ER01 / 2016.100. OD.1. T.1. 566 p.

    7. Correction and updating of PSA of power unit No. 5 of ZNPP. (2004). EP25 - 2004.210.OD.2. Power failure of the power unit with diesel generator failure. Appendix G2.1. 365 p.

     

  • Creative Commons License by Author(s)