Preview

Proceedings of the National Academy of Sciences of Belarus. Physical-technical series

Advanced search

Modeling the emergency processes proceeding in the containment of NPP with water-water energy reactor

https://doi.org/10.29235/1561-8358-2020-65-2-224-234

Abstract

The article presents the results of computational modeling of the development of accidents in the containment of NPP with water-water energy reactor (WWER) using the COCOSYS software. The containment of the Balakovo NPP with WWER-1000/V-320 was selected as the object of study. The results of the calculation of environmental parameters in the containment during a beyond design basis accident with a “large” leak from the primary circuit at the following initial events: break of the main circulation pipeline DN850 with a full cross section at the reactor inlet, with simultaneous failure of all AC sources including diesel generators for a long period, without operating personnel intervention. A comparison of the results of calculations with the results obtained using the ANGAR software certified by Rostekhnadzor is performed. The calculation results are in good agreement: emergency scenarios are similar; the maximum deviation from absolute pressure values is less than 10 %. Thus, it was concluded that the analysis of processes occurring in the NPP containment during an accident can be performed using the COCOSYS code. This software can be used to independent safety assessment of NPP required by the IAEA standards.

About the Authors

D. L. Tretinnikov
Joint Institute for Power and Nuclear Research – Sosny of the National Academy of Science of Belarus
Belarus

Denis L. Tretinnikov – Researcher

47/22 Prilesye district, Lugovaya Sloboda village council, Minsk district, 223063, Minsk region



A. V. Doinikova
Joint Institute for Power and Nuclear Research – Sosny of the National Academy of Science of Belarus
Belarus

Anastasiya V. Doinikova – Junior Researcher

47/22 Prilesye district, Lugovaya Sloboda village council, Minsk district, 223063, Minsk region



P. K. Nagula
Joint Institute for Power and Nuclear Research – Sosny of the National Academy of Science of Belarus
Belarus

Petr K. Nagula – Ph. D. (Engineering), Head of the Laboratory

47/22 Prilesye district, Lugovaya Sloboda village council, Minsk district, 223063, Minsk region



References

1. Kavun O. Yu., Soloviev S. L., Shevchenko R. A. Calculations of heat transfer and hydrodynamics, coupled neutron-physical and thermal-hydraulic calculations, simulation of non-stationary and emergency processes. Sovet po attestatsii programmnykh sredstv pri Rostekhnadzore 25 let na sluzhbe bezopasnosti: sbornik publikatsii [Software Certification Council under Rostekhnadzor 25 years in the security service: collection of publications]. Moscow, SEC NRS, 2016. 122 p. (in Russian).

2. Zvonarev Yu. A., Budaev M. A., Kobzar V. L., Konobev A. V., Shmelkov Yu. B.Calculation of parameters of the vapor-gas medium in the containment of the WWER-1000/V-320 in a severe beyond design basis accident taking into account the operation of the system of emergency filtered gas discharge. Sbornik trudov 9-y Mezhdunarodnoi nauchno-tekhnicheskoi konferentsii “Obespecheniye bezopasnosti AES s VVER” [Proc. of 9th Int. Scientific and Technical Conference “Safety of NPP with WWER”]. Podolsk, OKB “Gidropress”, 2015. Available at: http://www.gidropress.podolsk.ru/files/proceedings/mntk2015/autorun/article91-ru.htm (accessed 25 April 2019) (in Russian).

3. Semenovich O. V., Tishkovich A. N., Doinikova A. V. Containment Codes: Analytical Review. Preprint OIEYAI-72. Minsk, National Academy of Sciences of Belarus, JIPNR – Sosny, 2017. 35 p. (in Russian).

4. The main equipment of the reactor department. Available at: http://www.bib.convdocs.org/v10948/?cc=1&view=pdf (accessed 25 April 2019) (in Russian).

5. Technological systems of the reactor compartment. Part 1. Security systems. Available at: http://www.bib.convdocs.org/v10948/?cc=2&view=pdf (accessed 25 April 2019) (in Russian).

6. Technological systems of the reactor compartment. Part 2. Auxiliary systems. Available at: http://www.bib.convdocs.org/v10948/?cc=3&view=pdf (accessed 25 April 2019) (in Russian).

7. Alipchenkov V. M., Kiselev A. E., Tsaun S. V., Strizhov V. F., Tkachenko A. V., Konstantinov S. A., Maltsev M. B, Peresadko V. G., Kozlov D. I. Modeling the behavior of fission products in the containment using the SOKRAT computational complex. Sbornik trudov 7-i Mezhdunarodnoi nauchno-tekhnicheskoi konferentsii “Obespecheniye bezopasnosti AES s VVER” [Proc. of the 7th Int. Scientific and Technical Conference “Safety of NPP with WWER”]. Podolsk, OKB “Gidropress”, 2011. Available at: http://www.gidropress.podolsk.ru/files/proceedings/mntk2011/autorun/article42-ru.htm (accessed 25 April 2019) (in Russian).


Review

Views: 666


Creative Commons License
This work is licensed under a Creative Commons Attribution 4.0 License.


ISSN 1561-8358 (Print)
ISSN 2524-244X (Online)