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Investigation of ex-vessel core catcher for SBO accident in VVER-1000/V528 containment using MELCOR code

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Abstract

To mitigate consequences of core melting, an ex-vessel core catcher is investigated in this study. Instructions should be obeyed to cool down the corium caused by core melting. The corium destroys the reactor containment and causes radioactive materials to be released into the environment if it does not cool down well. It is important to build a core catcher system for the reception, localization, and cool down of the molten corium during a severe accident resulting from core melting. In this study, the role of a core catcher in the VVER-1000/v528 reactor containment during a station black out (SBO) accident is evaluated using the MELCOR1.8.6 code. In addition, parametric analyses of the SBO for (i) SBO accidents with emergency core cooling system (ECCS) operation, and (ii) without ECCS operation are performed. Furthermore, thermal–hydraulic analyses in dry and wet cavities with/without water are conducted. The investigations include the reduction of gases resulting from molten–corium–concrete interactions (H2, CO, CO2). Core melting, gas production, and the pressure/temperature in the reactor containment are assessed. Additionally, a full investigation pertaining to gas release (H2, CO, CO2) and the pressure/temperature of the core catcher is performed. Based on MELCOR simulations, a core cavity and a perimeter water channel are the best options for corium cooling and a lower radionuclide release. This simulation is also theoretically investigated and discussed herein. The simulation results show that the core catcher system in addition to an internal sacrificial material reduces the containment pressure from 689 to 580 kPa and the corresponding temperature from 394 to 380 K. Furthermore, it is observed that the amount of gases produced, particularly hydrogen, decreased from 1698 to 1235 kg. Moreover, the presence of supporting systems, including an ECCS with a core catcher, prolonged the core melting time from 16,430 to 28,630 s (in an SBO accident) and significantly decreased the gases produced.

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Abbreviations

MCCI:

Molten corium concrete interaction

BNPP:

Bushehr nuclear power plant

ECCS:

Emergency core cooling system

IVR:

In-vessel melt retention

EVR:

Ex-vessel melt retention

SM:

Sacrificial material

LOOP:

Loss of offside power

RPV:

Reactor pressure vessel

SBO:

Station black out

ACC:

Accumulator

CC:

Core catcher

PSD:

Pulse safety device

SG:

Steam generator

RCP:

Reactor coolant pump

References

  1. T.H. Vo, J.H. Song, An analysis of containment responses during a station blackout accident. J. Nucl. Sci. Technol. 54, 1074–1084 (2017). https://doi.org/10.1080/00223131.2017.1344584

    Article  Google Scholar 

  2. S.V. Svetlov, V.V. Bezlepkin, V.S. Granovsky. Core Catcher for Tianwan NPP with VVER-1000 reactor. Concept, Design and Justification. 11th International Conference on Nuclear Engineering Tokyo, Japan (2003). https://doi.org/10.1299/jsmeicone.2003.104

  3. M. Weimin, Y. Yuan, B.R. Sehgal, In-vessel melt retention of pressurized water reactors: Historical review and future research needs. Engineering (2016). https://doi.org/10.1016/J.ENG.2016.01.019

    Article  Google Scholar 

  4. O. Kumalanen, H. Tuomisto, T.G. Theofanous, In-vessel retention of corium of the Loviisa plant. Nucl. Eng. Design 169, 109–130 (1997). https://doi.org/10.1016/S0029-5493(96)01280-0

    Article  Google Scholar 

  5. T.G. Theofanous, C. Liu, S. Additon, In-vessel coolability and retention of a core melt. Nucl. Eng. Design 169, 1–48 (1997). https://doi.org/10.1016/S0029-5493(97)00009-5

    Article  Google Scholar 

  6. M.F. Rogov, I.V. Kukhtevich, V.B. Khabenskii et al., Analyzing the corium in the vessel of a VVER-640 reactor in a severe accident with a damaged core. Therm. Eng. 43, 888–892 (1996)

    Google Scholar 

  7. G. Löwenhielm, A. Engqvist, R. Espefalt, Accident management strategy in Sweden and verification implementation. Nucl. Eng. Design 148, 151–159 (1994). https://doi.org/10.1016/0029-5493(94)90106-6

    Article  Google Scholar 

  8. Yu.A. Zvonarev, D.F. Tsurikov, V.L. Kobzar, Numerical analysis of core catcher efficiency for VVER-1200. Phys. At. Nucl. 74, 1845–1853 (2011). https://doi.org/10.1134/S1063778811130084

    Article  Google Scholar 

  9. V.B. Khabensky, V.S. Granovsky, S.V. Bechta et al., Severe accident management concept of the VVER-1000 and the justification of corium retention in a Crucible-Type core catcher. Nuclear Eng. Tecnol. 41, 561–574 (2009). https://doi.org/10.5516/NET.2009.41.5.561

    Article  Google Scholar 

  10. V. Astafyeva, V. Bezlepkin, V. Kukhtevich et al. Computational analysis of core catcher behavior during corium relocations from reactor vessel. Proceedings of the 18th International Conference on Nuclear Engineering, ICONE18–29860, Xi'an, China. 597–603 (2010). https://doi.org/10.1115/ICONE18-29860

  11. A.A. Sulatsky, S.V. Bechta, V.S. Granovsky, Molten corium interaction with oxidic sacrificial material of vver core catcher. Proceedings of ICAPP ’05, Korea, 5240 (2005).

  12. A.A. Komlev, V.I. Almjashev, S.V. Bechta et al., New sacrificial material for ex-vessel core catcher. J. Nucl. Mater. 467, 778–784 (2015). https://doi.org/10.1016/j.jnucmat.2015.10.035

    Article  Google Scholar 

  13. M. Fischer, The severe accident mitigation concept and the design measures for core melt retention of the European Pressurized Reactor (EPR). Nucl. Eng. Design 230, 169–180 (2004). https://doi.org/10.1016/j.nucengdes.2003.11.034

    Article  Google Scholar 

  14. AEOI (Atomic Energy Organization of Iran). Final Safety Analysis Report (FSAR) for Bushehr VVER-1000 reactor, Chapter 6, Iran (2003).

  15. M. Rahgoshay, M. Hashemi-Tilehnoee, Pressure distribution in the containment of VVER-1000 during the first seconds of large break LOCA. Prog. Nucl. Energy 88, 211–217 (2016). https://doi.org/10.1016/j.pnucene.2016.01.010

    Article  Google Scholar 

  16. F. Faghihi, S.M. Mirvakili, S. Safaei-Arshi et al., Neutronics and sub-channel thermal-hydraulics analysis of the Iranian VVER-1000 fuel bundle. Prog. Nucl. Energy 87, 39–46 (2016). https://doi.org/10.1016/j.pnucene.2015.10.020

    Article  Google Scholar 

  17. S. Bagheri, F. Faghihi, M.R. Nematolahi et al., Assessment of thermal hydraulics parameters of the VVER-1000 during transient conditions. Int. J. Hydrogen Energy 41, 7103–7111 (2016). https://doi.org/10.1016/j.ijhydene.2016.02.066

    Article  Google Scholar 

  18. M.M. Hosseini, F. Faghihi, A. Pirouzmand et al., Innovative passive management of the Station Black-Out accident for VVER1000/V446 NPP and development of its emergency operating procedures. Prog. Nucl. Energy 126, 103–416 (2020). https://doi.org/10.1016/j.pnucene.2020.103416

    Article  Google Scholar 

  19. AEOI (Atomic Energy Organization of Iran), Final Safety Analysis Report (FSAR) for BNPP, Chapter 15, Iran (2015).

  20. R.O. Gauntt, J.E. Cash, R. K. Cole et al., MELCOR Computer Code Manuals, Vol. 1: Primer and Users’ Guide Version 1.8.6. (2005).

  21. R. Gharari, H. Kazeminejad, N. Mataji Kojouri et al., Study the effects of various parameters on hydrogen production in the WWER1000/V446. Prog. Nucl. Energy. 124, 103–370. (2020). https://doi.org/10.1016/j.pnucene.2020.103370

  22. R. Gharari, H. Kazeminejad, N. Mataji Kojouri et al., Assessment of new severe accident mitigation systems on containment pressure of the WWER1000/V446. Ann. Nucl. Energy 148, 107691 (2020). https://doi.org/10.1016/j.anucene.2020.107691

  23. P. Omidifard, A. Pirouzmand, K. Hadad et al., Analysis of loss of cooling and loss of coolant severe accident scenarios in VVER-1000/V446 spent fuel pool. Ann. Nucl. Energy 138, 107205 (2020). https://doi.org/10.1016/j.anucene.2019.107205

    Article  Google Scholar 

  24. O. Noorik, N. Jafari, M. Gei, Simulation of hydrogen distribution and effect of Engineering Safety Features (ESFs) on its mitigation in a WWER-1000 containment. Nucl. Sci. Tech. 30, 97 (2019). https://doi.org/10.1007/s41365-019-0624-0

    Article  Google Scholar 

  25. P.V. Petkov, D.V. Hristov, VVER-1000/V320 decay heat analysis involving TVS-M and TVSA fuel assemblies. Nucl. Eng. Design 238, 3227–3239 (2008). https://doi.org/10.1016/j.nucengdes.2008.06.012

    Article  Google Scholar 

  26. A.E. Stefanova, B.P. Groudev, P.P. Atanasova, Comparison of hydrogen generation for TVSM and TVSA fuel assemblies for water water energy reactor (VVER)-1000. Nucl. Eng. Design 239, 180–186 (2009). https://doi.org/10.1016/j.nucengdes.2008.08.001

    Article  Google Scholar 

  27. P. Groudev, A.E. Stefanova, R.V. Gencheva, Investigation of VVER 1000 core degradation during SBO accident scenario in case of pressurizer SV stuck in open position. Technical Meeting on “Fuel Behaviour and Modelling Under Severe Transient and LOCA Conditions” Ibaraki, Japan, (2011).

  28. P. Groudev, A.E. Stefanova, R.V. Gencheva, Investigation of VVER 1000 fuel behavior in severe accident condition. IAEA Technical Meeting “Modelling of Water-Cooled Fuel Including Design-Basis and Severe Accidents” 28 October – 1 November, Chengdu, China (2013).

  29. AEOI (Atomic Energy Organization of Iran). Atomenergoproekt, Preliminary safety analysis report of BNPP's VVER-1000 reactor, engineered safety features. Chapter 6, ed. Moscow (2017).

  30. Atom Energo Proekt, Probabilistic Safety Assessment of BNPP’s VVER-1000 Reactor (Ministry of Russian Federation of Atomic Energy, Moscow, 2014).

    Google Scholar 

  31. A. Petruzzi, F. Auria, Thermal-hydraulic system codes in nuclear reactor safety and qualification procedures. Sci Technol Nuclear Installations. 2008, 460795 (2008). https://doi.org/10.1155/2008/4607995

    Article  Google Scholar 

  32. N.E. Todreas, M.S. Kazimi, Nuclear Systems I: Thermal Hydraulic Fundamentals (Taylor & Francis, Milton Park, 1993).

    Google Scholar 

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Authors and Affiliations

  1. Department of Nuclear Engineering, School of Mechanical Engineering, Shiraz University, Shiraz, 71936-16548, Iran

    Farhad Salari, Ataollah Rabiee & Farshad Faghihi

  2. Radiation Research Center, Shiraz University, Shiraz, Iran

    Farshad Faghihi

  3. Ionizing and Non-Ionizing Research Center, Shiraz University of Medical Science, Shiraz, Iran

    Farshad Faghihi

Authors
  1. Farhad Salari
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  3. Farshad Faghihi
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Correspondence to Farshad Faghihi.

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Salari, F., Rabiee, A. & Faghihi, F. Investigation of ex-vessel core catcher for SBO accident in VVER-1000/V528 containment using MELCOR code. NUCL SCI TECH 32, 43 (2021). https://doi.org/10.1007/s41365-021-00879-x

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  • DOI: https://doi.org/10.1007/s41365-021-00879-x

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