Assessment of operation of safety channel signal cables at nuclear power plants under fire conditions
https://doi.org/10.22227/PVB.2020.29.04.51-58
Abstract
Introduction. Signal cables of safety systems, installed at nuclear power plants (NPPs), retain the ability to conduct modulated signals during the time period needed to switch the reactor facility to a safe mode. However, the ability of signal cables to transmit signals correctly in the high temperature gas medium, which is typical for the early stage of a room fi re, has not been exposed to research.
Aims and objectives. The co-authors offer a theoretical assessment of the ability of NPP safety system cables to correctly transmit modulated electric signals if exposed to fi re and current loads. The theoretical research into the temperature of the conductor of a signal cable at the initial stage of fi re has been performed towards this end.
Theoretical background. The steady state heat conduction equation, describing heat transmission from the cable core to the environment through the cylinder-shaped insulation layer, is used to measure the temperature of the cable strand.
Results and discussion. Temperature dependences describing the relation between the temperature of the conductor of a single - strand and single-wire cable KNEPng(А)-HF on the gas medium temperature are obtained. Relations between the temperature of the gas medium in the room on fi re and the current intensity in the electric cable (if the cable is laid vertically) are presented with account taken of the dependence between the specifi c resistance of the wire and the temperature if the maximal permissible operating temperature of cable strands is 70 °С, the maximal permissible operating temperature of cable strands in the overload operation mode is 80 °С, and the maximal cable strand heating temperature is equal to 160 °С when the short-circuit failure occurs. Maximal current intensity values are obtained for various operating modes in the condition of temperatures typical for the initial stage of an indoor fire, they allow to correctly conduct modulated signals within the time period needed to switch the reactor facility to a safe mode.
Conclusions. The developed mathematical model and results of numerical experiments allow to assess the infl uence of the temperature in the room of a nuclear power plant in case of fi re on the ability of a signal cable of the safety system to transfer undistorted modulated signals depending on current loads and signal cable laying patterns (whether it is laid vertically or horizontally), and also to expand the range of the room temperature dependence on the current load provided in Electrical Installations Code (EIC).
About the Authors
O. S. LebedchenkoRussian Federation
Olga S. LEBEDCHENKO, Cand. Sci. (Leg.), Associate Professor, Associate Professor of Thermal Physics and Hydraulic Department
ID RISC: 770128
Borisa Galushkina st., 4, Moscow, 129366
V. I. Zykov
Russian Federation
Vladimir I. ZYKOV, Dr. Sci. (Eng.), Professor, Laureate of the Russian Federation Government Prize in Science and Technology, Honored Worker of Higher Education of the Russian Federation, Professor of Department of SEASS
ID RISC: 328773
Borisa Galushkina st., 4, Moscow, 129366
S. V. Puzach
Russian Federation
Sergey V. PUZACH, Dr. Sci. (Eng.), Professor, Honored Scientist of the Russian Federation, Head of Thermal Physics and Hydraulic Department
ID RISC: 18265; Scopus Author ID: 7003537835; ResearcherID: U-2907-2019
Borisa Galushkina st., 4, Moscow, 129366
References
1. Meshchanov G.I., Kholodnyy S.D. Analysis of the combustion characteristics of polymer insulation of cables during their group laying. Cables and wires. 2010; 6(325):10-14. (rus.).
2. Khasanov I.R., Varlamkin A.A. Experimental methods for determining the fire resistance of cable penetrations in case of fire, taking into account the influence of load currents. Collection of materials: XVII All-Russian scientific-practical conference “Problems of predicting emergency situations”. Moscow, October 30–31, 2018 Moscow, FKU Center “Antistikha” Emercom of Russia, 2018; 77-78. (rus.).
3. Puzach S.V., Lebedchenko O.S. Mathematical modeling of the dynamics of hazardous fire factors during passive fire protection in the main buildings of nuclear power plants with water-cooled reactors: monograph. Moscow, Academy of the State Fire Service Emercom of Russia, 2019; 304. (rus.).
4. Titkov V.V., Dudkin S.M. Cable lines 6-10 kV and over. Influence of laying methods on temperature conditions. The News of Electrical Engineering. 2012; 3(75):2-4. URL: http://www.news.elteh.ru/arh/2012/75/10.php (rus.).
5. University complex as a regional center of education, science and culture: Materials of the All-Russian scientific and methodological conference. Orenburg, OSU Publ., 2018. URL: https://conference. osu.ru/archive/publications.html?detailed=14 (rus.).
6. Zykov V.I., Anisimov Yu.N., Malashenkov G.N. Fire protection of electrical networks from leakage currents. Reducing the risk of death in fires: Materials of the XVIII scientific and practical conference. Part 1. Moscow, VNIIPO Publ., 2003; 182-185. (rus.).
7. Finger H. Advances in fire hazard testing of electrical equipment. IEEE Electrical Insulation Magazine. 1986; 2(4):24-29. DOI: 10.1109/MEI.1986.290418
8. Gusev S.S. Safe management of nuclear power plants. Electrical equipment: exploitation and repair. 2017; 12:42-45. (rus.).
9. Benchmark Analysis for Condition Monitoring Test Techniques of Aged Low Voltage Cables in Nuclear Power Plants. Final Results of a Coordinated Research Project. IAEA-TECDOC-1825. Vienna, International Atomic Energy Agency, 2017.
10. Cable Ageing in Nuclear Power Plants. Report on the first and second terms (2012-2017) of the NEA Cable Ageing Data and Knowledge (CADAK) Project. NEA/CSNI/R(2018)8. Nuclear Energy Agency, 2018; 58. URL: https://www.oecd.org/officialdocuments/publicdisplaydocumentpdf/?cote=NEA/CSNI/R(2018)8&docLanguage=En
11. Csanyi E. Internal electrical systems within nuclear power plant stations (power sources). Electrical Engineering Portal. 2019. URL: https://electrical-engineering-portal.com/electrical-systems-nuclear-power-plant-stations
12. Puzach S.V., Lebedchenko O.S., Sizukhin S.V. Substantiating passive fire protection technology for the main buildings of nuclear power plants with water-cooled reactors based on calculating fire resistance of enclosing structures. Fire and emergencies: prevention, elimination. 2020; 1:22-29. (rus).
13. Lebedchenko O.S. Substantiation of features of technology of passive fire protection of the main buildings of nuclear power plants with water reactors. Proceedings of 28th International Scientific-Technical Conference “Safety Systems – 2019”. Moscow, Academy of the State Fire Service Emercom of Russia, 2019; 291-296. (rus.).
14. Lebedchenko O.S. Assessment of ensuring the correct operation of safety channel cables of nuclear power plants in a fire. Collection of materials of the VIII Scientific and practical conference “Roitman readings”. Moscow, 05 March 2020. Moscow, Academy of the State Fire Service Emercom of Russia, 2020; 72-75. (rus.).
15. Cable Research in Light Water Reactor Related to Mechanisms of Cable Degradation: Understanding of role of material type, history, and environment, as well as accelerated testing limitations. US DOE/ NRC/EPRI, 2013.
16. Assessing and Managing Cable Ageing In Nuclear Power Plants. NP-T-3.6. Vienna, International Atomic Energy Agency, 2012. URL: https://www-pub.iaea.org/MTCD/Publications/PDF/Pub1554_ web.pdf
17. Celina M.C., Gillen K.T., Lindgren E.R. Nuclear Power Plant Cable Materials: Review of Qualification and Currently Available Aging Data for Margin Assessments in Cable Performance. SAND2013-2388. Sandia National Laboratories, 2013. DOI: 10.2172/1096518
18. Brown J.R., Bernstein R., White G.V., Glover S.F., Neely J.C., Pena G. et al. Submerged Medium Voltage Cable Systems at Nuclear Power Plants: A Review of Research Efforts Relevant to Ageing Mechanisms and Condition Monitoring. SAND2015-1794. Sandia National Laboratories, 2015. DOI: 10.2172/1177756
19. Ageing Management of Cable in Nuclear Generating Stations. 13395-REP-00001 Rev. 0. Canadian Nuclear Safety Commission, 2012; 131. URL: https://www.nuclearsafety.gc.ca/eng/pdfs/about/researchsupport/reportabstracts/RSP-0284-Final-report.pdf
20. Kutateladze S.S. Fundamentals of the heat transfer theory. Moscow, Atomizdat Publ., 1979; 416. (rus.).
Review
For citations:
Lebedchenko O.S., Zykov V.I., Puzach S.V. Assessment of operation of safety channel signal cables at nuclear power plants under fire conditions. Pozharovzryvobezopasnost/Fire and Explosion Safety. 2020;29(4):51-58. (In Russ.) https://doi.org/10.22227/PVB.2020.29.04.51-58