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Investigation on primary side oriented accident management measures in a hypothetical station blackout scenario for a VVER-1000 pressurized water reactor

  • P. Tusheva , F. Schäfer , N. Reinke , E. Altstadt , U. Rohde , F. P. Weiss and A. Hurtado
Published/Copyright: April 5, 2013
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Kerntechnik
From the journal Kerntechnik Volume 75 Issue 1-2

Abstract

As a consequence of a total loss of AC power supply (station blackout) at a VVER-1000 leading to unavailability of major active safety systems, the safety criteria ensuring the safe operation of the nuclear power plant would be violated and core heat-up with possible core degradation could occur. A dedicated accident management measure (primary side depressurization) can be applied to reduce the primary pressure and to activate the injection from the passive emergency core cooling systems (accumulators). The analyses presented in this paper are aiming at both a detailed investigation of the accident sequence, taking into account the depressurization of the primary circuit, and the possibilities to prevent or at least to mitigate a damage of the reactor core so as to gain additional time for taking necessary countermeasures. The analyses are performed using the codes ASTEC and ATHLET developed by IRSN (Institut de Radioprotection et de Sûreté Nucléaire) and GRS (Gesellschaft für Anlagen- und Reaktorsicherheit mbH).

Kurzfassung

Bei einem Totalausfall der Stromversorgung (station blackout) in einem VVER-1000 stehen wichtige aktive Sicherheitssysteme nicht zur Verfügung. In der Folge kann es zu einer Kernaufheizung und zu Kernschäden kommen. Bei einem derartigen Störfall kann als Notfallmaßnahme die primäre Druckentlastung durchgeführt werden, um den Primärdruck zu reduzieren und so die passive Notkühleinspeisung (Druckspeicher) zu aktivieren. Das Ziel der hier vorgestellten Analysen ist eine detaillierte Untersuchung des Störfallablaufes unter Berücksichtigung der Notfallprozedur „Primäre Druckentlastung“ und möglicher Maßnahmen, um schwere Kernschäden zu vermeiden oder zumindest zu verzögern und um mehr Zeit für das Einleiten von weiteren Notfallmaßnahmen zu gewinnen. Die Analysen wurden mit den vom IRSN (Institut de Radioprotection et de Sûreté Nucléaire) und von der GRS (Gesellschaft für Anlagen- und Reaktorsicherheit mbH) entwickelten Codes ASTEC und ATHLET durchgeführt.

References

1 Giordano, P.; Larbi, H.; Kadri, D.: ASTEC-V1/DOC/01-15, ASTECV1 – CESAR: Two phase flow thermal, hydraulic module- Version 1.0 – Description of physical and numerical modelling, Rev 0, Technical note 01/35 (2001) CadaracheSearch in Google Scholar

2 Pignet, S.: ASTEC-V1/DOC/02-04, Description of thermal hydraulic models of DIVA. Technical note IRSN/DRS/SEMAR 02/31 (2002) CadaracheSearch in Google Scholar

3 Lerchl, G.; Austregesilo, H.: ATHLET User's Manual. Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) mbH (2001) Cologne, GermanySearch in Google Scholar

4 Tusheva, P.; Reinke, N.; Altstadt, E.; Schäfer, F.; Weiß, F.-P.; Hurtado, A.: Analysis of Severe Accidents in VVER-1000 Reactors using the Integral Code ASTEC. Proceedings of the 17th International Conference on Nuclear Engineering, ICONE17, 12–16 July 2009, Brussels, Belgium10.1115/ICONE17-75563Search in Google Scholar

5 Theofanous, T. G.; Liu, C.; Additon, S.; Angelini, S.; Kymäläinen, O.; Salmassi, T.: In-vessel coolability and retention of a core melt. Nucl. Eng. and Design169 (1997) 1–4810.1016/S0029-5493(97)00009-5Search in Google Scholar

6 Bechta, S. V.; Granovsky, V. S.; Khabensky, V. B.; Krushinov, E. V.; Vitol, S. A.; Strizhov, V. F.; Bottomley, D.; Fischer, M.; Piluso, P.; Miassoedov, A.; Tromm, W.; Altstadt, E.; Willschutz, H. G.; Fichot, F.; Kymalainen, O.: VVER steel corrosion during in-vessel retention of corium melt. European Review Meeting on Severe Accident Research (ERMSAR Meeting), 23–25 September 2008, Nessebar, BulgariaSearch in Google Scholar

7 Tusheva, P.; Schäfer, F.; Reinke, N.; Rohde, U.: Investigation on Accident Management Measures for VVER-1000 Reactors. 19th AER Symposium on VVER Reactor Physics and Reactor Safety, September 21–25 2009, St. Constantine and Elena resort, Varna, BulgariaSearch in Google Scholar

Received: 2009-11-18
Published Online: 2013-04-05
Published in Print: 2010-03-01

© 2010, Carl Hanser Verlag, München

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  3. Summaries/Kurzfassungen
  4. Summaries
  5. Technical Contributions/Fachbeiträge
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  7. Investigation on primary side oriented accident management measures in a hypothetical station blackout scenario for a VVER-1000 pressurized water reactor
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  13. Chebyshev polynomials expansion method for solving the one-dimensional transport equation in spherical geometry
  14. Heuristic geometric “eigenvalue universality” in a one-dimensional neutron transport problem with anisotropic scattering
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https://doi.org/10.3139/124.110077

Articles in the same Issue

  1. Contents/Inhalt
  2. Contents
  3. Summaries/Kurzfassungen
  4. Summaries
  5. Technical Contributions/Fachbeiträge
  6. European clearinghouse on nuclear power plants operational experience feedback
  7. Investigation on primary side oriented accident management measures in a hypothetical station blackout scenario for a VVER-1000 pressurized water reactor
  8. Heat transfer to the building structures of the Ignalina NPP accident localisation system
  9. Algorithmic determination of fuel rod cladding burst time at elevated temperatures
  10. Development of a decommissioning strategy for the MR research reactor
  11. Neutron transmutation doping conceptual design
  12. Design optimization of shell-and-tube heat exchangers using single objective and multiobjective particle swarm optimization
  13. Chebyshev polynomials expansion method for solving the one-dimensional transport equation in spherical geometry
  14. Heuristic geometric “eigenvalue universality” in a one-dimensional neutron transport problem with anisotropic scattering
  15. An analytical solution for the one-dimensional time-dependent SN transport equation for bounded and unbounded domains in cartesian geometry
  16. Accurate critical slab calculations for various degrees of anisotropy and for different reflection coefficients
  17. Technical Notes/Technische Mitteilungen
  18. The boundary problem in the 1D-CANDLE burn-up reactor
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