V. I. Skalozubov, V. Yu. Kochnyeva,
Alali Mohammad, Algerby Rabia K. Ali
Odessa National Polytechnic University,
1, Shevchenko ave, Odesa, 65044, Ukraine
DOI: doi.org/10.31717/2311-8253.21.3.2
Abstract
The need to optimize the test frequency of thermal mechanical equipment of active safety systems of nuclear power plants is determined by the fact that, on the one hand, an increase in the test frequency reduces the probability of “latent” defects, critical for reliability and operability, in the “standby” mode of performing safety functions, and on the other hand, the probability of failure because of equipment wear during testing increases. Based on operating experience and the actual technical condition of the equipment, a method for optimizing the test frequency of active safety systems during the over-design operation period is presented. The calculated substantiations clarified that the optimal test frequency is two times less than the design onewith the extension of the service life; and when the operation life is extended for 12 and 20 years, the optimal test frequency decreases by 65% and 95%, respectively.
Keywords: active safety system, optimization, test frequency, periodicity, operation life extension, nuclear power plant.
References
1. Fridman N. А., Skalozubov V. I. (1998). [Substantiation of the control periodicity of safety systems at nuclear power plants with regenerative methods]. Nuclear and Radiation
Safety, no. 1, pp. 148–154. (in Russ.)
2. Komarov Ju. А., Vasil’chenko V. N., Skalozubov V. I., Kolykhanov V. N. (1999). [Algorithms and computational softwares of methodology for optimizing the control periodicity of NPP safety related systems]. Nuclear and Radiation Safety, no. 5, pp. 4–8. (in Russ.)
3. Komarov Ju. А., Skalozubov V. I., Kolykhanov V. N. (2000). [Fundamentals of the methodology for optimizing the control periodicity of safetyrelated systems]. Nuclear and Radiation Safety, no. 1, pp. 79–86. (in Russ.)
4. Bilej D. V., Kolykhanov V. N., Skalozubov V. I., Fridman N. А. (2004). [Probabilistic methods for optimizing scheduled inspections and tests of heat engineering equipment of safety systems during reactor operation at power] Nuclear and Radiation Safety, no. 3, pp. 46–55. (in Russ.)
5. Bilej D. V., Dragan G. S., Komarov Ju. А., Skalozubov V. I. (2006). [Risk-informed approach to optimize scheduled inspections of heating equipment of safety related systems
of nuclear installations]. Nuclear and Radiation Safety, no. 2, pp. 21–28. (in Russ.)
6. Kovrizhkin Ju. L., Kolykhanov V. N., Kochneva V. Ju., Skalozubov V. I. (2007). [Generalized method for optimizing the test periodicity of NPP safety systems]. Nuclear
and Radiation Safety, no. 2. (in Russ.)
7. Kovrizhkin Ju. L., Gablaya T. V., Dragan G. S., Skalozubov V. I. (2006). [Methodology for reviewing the periodicity and scope of scheduled repairs and tests of thermal mechanical equipment of VVER-1000 (B-320) safety systems]. Nuclear and Radiation Safety, no. 3, pp. 90–97. (in Russ.)
8. Skalozubov V. I., Kozlov I. L., Chulkin O. O. (2017). [Review of periodicity of routine tests of safety systems of nuclear power plants in the extra-design period of operation]. Problems of Atomic Science and Technology, no. 5, pp. 53–56. (in Ukr.)
9. Kolykhanov V. N., Komarov Ju. А., Slyusenko M. E., Nikolajchuk A., Skalozubov V. I. (2001). [To the issue of the optimization of the boron solution concentration control
system at VVER power units]. Nuclear and Radiation Safety, no. 1, pp. 44–48. (in Russ.)
10. Komarov Ju. А., Pyshnyj V. M., Skalozubov V. I., Fol’tov I. M. (2004). [Development of a branch standard for reducing the periodicity of complex leak testing of a VVER
containment system based on probabilistic methods]. Nuclear and Radiation Safety, no. 2, pp. 73–79. (in Russ.)
11. Bilej D. V., Komarov Ju. А., Pyshnyj V. M., Kolykhanov V. N., Kochneva V. Ju., Skalozubov V. I. (2005). [Draft branch standard for optimizing operational control of
NPP pipeline metal based on risk-informed approaches]. Nuclear and Radiation Safety, no. 4, pp. 71–81. (in Russ.)
12. Agejkina Е. S., Dragan G. S., Kovrizhkin Ju. L., Skalozubov V. I. (2006). [Calculated estimates of the residual life of separate thermal mechanical equipment at NPP with
VVER] Nuclear and Radiation Safety, no. 2, pp. 32–36. (in Russ.)
13. Kovrizhkin Ju. L., Skalozubov V. I. (2004). [Methodology for revewing permissible loading cycles for equipment and pipelines at NPP with VVER]. Nuclear and Radiation
Safety, no. 3, pp. 93–98. (in Russ.)
14. Zarytskyi M. S., Klochko V. V., Kovryzhkin Ju. L., Komarov Ju. O., Pyshnyi V. M., Aheikina K. S., Skalozubov V. I. (2006). [Draft NNEGC “Energoatom” branch standard for
cyclic load rates for NPP pipelines] Nuclear and Radiation Safety, no. 2, pp. 51–54. (in Ukr.)
If the article is accepted for publication in the journal «Industrial Heat Engineering» the author must sign an agreement on transfer of copyright. The agreement is sent to the postal (original) or e-mail address (scanned copy) of the journal editions.
Authors retain copyright and grant the journal right of first publication with the work simultaneously licensed under a Creative Commons Attribution License International CC-BY that allows others to share the work with an acknowledgement of the work’s authorship and initial publication in this journal.