Blackout Accident Management Strategies at Nuclear Power Plants

V. І. Skalozubov, V. Yu. Grib, A. V. Korolev, T. V. Gablaya, V. Yu. Kochneva

Odessa National Polytechnic University,
1, Shevchenko av., Odesa, 65044, Ukraine

DOI: doi.org/10.31717/2311-8253.19.2.2

Abstract

Technical shortcomings of nuclear power plants (NPP) with boiling water reactors and the inadequate training of operating staff for blackout accident management are among the main causes of severe accidents and destructive explosions at the Fukushima-Daiichi NPP. The blackout at Fukushima-Daiichi NPP was a consequence of the site flooding because of combined effect of the earthquake (about 9 points in the epicenter at a distance of 160–180 km from coast) and tsunami with a height of more than 14 m near the coast. The Fukushima-Daiichi site is placed at a height of 10 m above sea level, and there is a system of breakwaters with a height of more than 4 m above sea level. According to design calculations, the maximum wave height off the coast is about 5 m. Therefore, the accident was great surprise for the operating organization Tokyo Electric Power Company, and it revealed unpreparedness of technical means and staff in preventing consequences of the initial accident event. After Fukushima-Daiichi accident double inspections were hold at all US nuclear power plants. They also demonstrated insuffi-cient preparedness of technical means and staff for blackout accident management. Analysis of current and developed guidelines/instructions for the severe accident management at reactor facilities has revealed that the accepted blackout accident management strategies at NPP with water-water energetic reactor (VVER) are not substantiated and not effective enough. A comprehensive blackout accident management strategy is described in the paper. The strategy is based on an integrated approach to ensuring the safety functions of afterheat removal from the reactor and maintaining the required level of boiler water in the steam generator. The strategy is realised by alternative emergency steam-driven feed pumps at steam generator pressure of more than 0.3 MPa, and by afterheat removal passive systems based on the principles of natural circulation at lower pressures.
Practical implementation of the proposed blackout accident management strategy determines the need of additional experimental design qualification of new passive safety systems

Keywords: accident management, blackout, nuclear power plant.

References

1. IAEA International Fact Expert Mission of the FukushimaDaiichi NPP Accident Following the Great East Japan Earthquake and Tsunami. IAEA Mission Report. IAEA, 2011, 160 p.

2. Skalozubov V. I., Klyuchnikov A. A., Vashchenko V. N., Yarovoy S. S. (2012). Analiz prichin i posledstviy avarii na AES Fukushima kak faktor predotvrashcheniya tyazhelykh avariy v korpusnykh reaktorakh [Analysis of the causes and consequences of the accident at Fukushima NPP as a factor in the prevention of severe accidents in tank reactors]. Chornobyl: ISP NPP NAS of Ukraine, 280 p. (in Russ.)

3. Skalozubov V.I., Oborsky G.A., Kozlov I. L., Vashchenko V. N., Gablaya V. V., Kochneva V. Yu. (2013). Kompleks metodov pereotsenki bezopasnosti atomnoy energetiki Ukrainy s uchetom urokov ekologicheskikh katastrof v Chernobyle i Fukusime [Complex of methods for reassessing the safety of nuclear energy in Ukraine, taking into account the lessons of environmental disasters in Chornobyl and Fukushima]. Odesa: Astroprint, 244 p. (in Russ.)

4. Skalozubov V. I., Klyuchnikov A. A., Komarov Yu. A., Shavlakov A. V. (2010). Nauchno-tekhnicheskie osnovy meropriyatiy povysheniya bezopasnosti AES s VVER [Scientific and technical basis of measures to improve the safety of NPPs with VVER]. Chornobyl: ISP NPP NAS of Ukraine, 200 p. (in Russ.)

5. USSR State Committee for the Supervision of Safe Work in the Nuclear Power Industry (1989). PNAE G-7-002-86. Norms for calculating the strength of equipment and pipelines of nuclear power plants. Moscow: Energoatomizdat, 525 p. (in Russ.)

6. USSR State Committee for the Supervision of Safe Work in the Nuclear Power Industry (1989). PNAE G-5-006-87. Standards for design of seismic resistant nuclear power plants. Moscow: Energoatomizdat, 24 p. (in Russ.)

7. Naffaa H. M., Dubkovsky V. A. (2014). Obosnovanie vybora skhemnogo resheniya i geometricheskikh parametrov SPOT GO VVER-1000 [Justification of the choice of circuit design and geometrical parameters of CARPS VVER-1000]. Yaderna ta radiatsiina bezpeka [Nuclear and Radiation Safety], vol. 63, no. 3, pp. 19–23. (in Russ.)

8. Naffaa Kh. M., Gerliga V. A., Shevelev D. V., Balashevsky A. S. (2013). Otsenka effektivnosti sistemy passivnogo otvoda tepla ot zashchitnoy obolochki RU s VVER v usloviyakh dlitelnogo obestochivaniya [Evaluation of the effectiveness of the system of passive heat removal from the VVER RP protective shell under conditions of prolonged de-energization]. Yaderna ta radiatsiina bezpeka [Nuclear and Radiation Safety], vol. 58, no. 2, p. 27–31. (in Russ.)

9. Naffaa H. M., Shevelev D. V., Balashevsky A. S. (2014). Raschetnoe modelirovanie raboty i otsenka effektivnosti sistemy passivnogo otvoda tepla ot germoobema (SPOT GO) pri razryve paroprovoda ostrogo para s neizolyatsiey avariynogo PG po pitvode na AES s VVER-1000 [Computational modeling of work and assessment of the efficiency of the passive heat removal system from the containment CARPS in case of rupture of the steam line with non-isolation of the emergency SG at the power supply at VVER-1000 NPPs]. Globalnaya yadernaya bezopasnost [Global Nuclear Safety], vol. 10, no. 1, pp. 5–9. (in Russ.)

10. FGUP-OKBM-AEP (2008). Zadachi obosnovaniya SPOT zashchitnoy obolochki dlya AES novogo pokoleniya [The tasks of justifying the ARPS of the containment for NPPs of the new generation]. Proceedings of the “Ensuring the safety of NPPs with WWER” (Podolsk, Russia). Podolsk: Gidropress. (in Russ.)

11. Naffaa H. M., Dubkovsky V. A. (2014). Klassifikatsiya sistem passivnogo otvoda ostatochnykh teplovydeleniy ot zashchitnykh obolochek yadernykh reaktorov [Classification of systems for passive removal of residual heat from the protective shells of nuclear reactors]. Odes’kyi Politechnichnyi Universytet. Pratsi, vol. 43, no. 1, pp. 104–112. (in Russ.)

12. NUREG/CR6519. Screening Reactor Steam / Water Piping Systems for Water Hammer. U. S. Nuclear Regulatory Commission, 1997, 49 p.

13. Korolev A. V., Derevyanko O. V. (2014). Reserve backup of steam generators of nuclear power plants in the conditions of electrical powering of the power unit. Yaderna ta radiatsiina bezpeka [Nuclear and Radiation Safety], vol. 62, no. 2, pp. 10–12. (in Russ.)

14. Mazurenko A. S., Skalozubov V. I., Pirkovsky D. S., Chulkin O. A., Zhou Huiyuy (2017). Analysis of the applicability of the results of experimental studies of hydrodynamics to pump systems of thermal and nuclear power plants. Yaderna enerhetyka ta dovkillia [Nuclear Power and the Environment], vol. 9, no. 1, pp. 49–53. (in Russ.)

15. Posobie sluzhby podgotovki personala Balakovskoy AES po ekspluatatsii energobloka VVER-1000. Tom 2 [Manual service personnel training Balakovo NPP for the operation of the power unit VVER-1000. Volume 2]. Ministry of the Russian Federation for Atomic Energy; Rosenergoatom, 2009, 382 p. (in Russ.)

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Published
2019-08-31

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