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Problems of the emergency thermal load calculation in the channels of the water-cooled nuclear reactors
G. I. Sharaevsky*Abstract: Representations about the physical mechanism of the heat transfer crisis under forced motion of two-phase flow in heated channels are considered. Analysis of known approaches is carried out and methodical bases of the development and application of recommendations on calculation and control of the heat transfer crisis at NPPs with WWER is proposed.
Keywords: water-cooled nuclear reactor, two-phase flow of coolant, heat transfer crisis.
References:1. À.À. Kliuchnikov et al. Thermophysics of Nuclear Power Plant Safety (Kyiv: Institute for Safety Problems of NPP, NASU, 2010) 484 p. (Rus)
2. V.P. Bobkov. Critical heat flow at water boiling in channels. Current state, characteristic patterns, unsolved problems and ways to solve them. Òåploenergetika 2 (2015) 10. (Rus) https://doi.org/10.1134/S0040363615020022
3. V.P. Bobkov, V.N. Vinogradov, Î.À. Ziatnina, N.V. Kozina. Method for estimating the crisis in channels of a complex cross-section profile. Òåploenergetika 3 (1995) 37. (Rus)
4. V.P. Bobkov. À.O. Sudnitsyn, Ì.Î. Sudnitsyna. Numerical and analytical description of critical heat flows in channels. Àtomic Energy 84(2) (1998) 98. (Rus) https://doi.org/10.1007/BF02414196
5. V.P. Bobkov. Method for describing and calculating critical heat fluxes in annular channels in a wide range of parameters. Òåploenergetika 7 (2012) 1. (Rus)
6. V.P. Bobkov, V.N. Vinogradov, P.L. Kirillov, I.P. Smogalev. Critical heat fluxes in triangular beams of rods (skeleton table, version 1997). Òåploenergetika 11 (1999) 54. (Rus)
7. V.P. Bobkov et al. Substantiation and verification of the heat exchange crisis model in the beams of the thermo-hydraulic code KORSAR. Òåploenergetika 3 (2003) 35. (Rus)
8. V.Å. Doroshchuk. Heat Exchange Crises in Boiling Water in Pipes. 2-nd åd. (Ìoskva: Energoatomizdat, 1983) 120 p. (Rus)
9. D.C. Groeneveld et al. The 1995 look-up table for critical heat flux in tubes. Nucl. Eng. and Design 163 (1996) 1. https://doi.org/10.1016/0029-5493(95)01154-4
10. À.V. Nosovsky et al. Thermophysics of NPP Resource (Kyiv: Institute for Safety Problems of NPP, NASU, 2017) 624 p. (Rus) http://www.ispnpp.kiev.ua/teplofizyka-2017/
11. À.À. Kliuchnikov et al. Thermophysics of Active Zones Reliability (Kyiv: Institute for Safety Problems of NPP, NASU, 2015) 772 p. (Rus) http://www.ispnpp.kiev.ua/teplofizika-nadeznosti-atkivnyh-zon/
12. G.I. Sharaevsky. Methodology for determining the boiling point in FA by analyzing acoustic noise. Nuclear and Radiation Safety 3(71) (2016) 48. (Rus) http://sstc.com.ua/documents/journal/2016/3/text/9_3_2016_text.pdf
13. V.P. Bobkov, À.D. Åfanov, R.S. Pometko, I.P. Smogalev. Modified table for critical heat fluxes in assemblies of fuel rods in triangular packaging. Òåploenergetika 4 (2011) 43. (Rus)
14. V.P. Bobkov, I.P. Smogalev. Tabular method for describing critical heat flows in square-packed fuel assemblies. Àtomic Energy 94(5) (2003) 355. (Rus) https://doi.org/10.1023/A:1025096113634
15. V.P. Bobkov, À.D. Åfanov, I.P. Smogalev, R.S. Pometko. Table for critical heat fluxes in square-packed fuel-element assemblies. Àtomic Energy 99(1) (2005) 472. (Rus) https://doi.org/10.1007/s10512-005-0233-3
16. L. Òîng. The Boiling Crisis and the Critical Heat Flux (Ìoskva: Àòîmizdat, 1976) 100 p. (Rus)
17. À.À. Kliuchnikov et al. Thermophysics of Nuclear Reactor Accidents (Kyiv: Institute for Safety Problems of NPP, NASU, 2012) 528 p. (Rus) http://www.ispnpp.kiev.ua/teplofizyka-avarij-yadernyh-reaktorov/
18. À.À. Kliuchnikov et al. Thermophysics of Reactor Facilities Damages (Kyiv: Institute for Safety Problems of NPP, NASU, 2013) 528 p. (Rus) http://www.ispnpp.kiev.ua/teplofizika-povrezhdenij-reaktornyh-ustanovok/