APPROACHES TO MODELING CONDITIONS OF THERMOACOUSTIC INSTABILITY IN NON-EQUILIBRIUM TWO-PHASE COOLANT OF NUCLEAR REACTORS
Abstract
The occurrence of thermoacoustic instability in the non-equilibrium two-phase flow of the coolant can significantly affect the reliability and integrity of the nuclear reactor's internal devices. At present, the development of adequate and justified methods for modeling thermoacoustic instability in the active zone of a nuclear reactor is an urgent issue. The purpose of the study is to develop a criterion method for determining the conditions for the occurrence of TAN in the active zone of nuclear reactors, which will increase operational safety and provide an opportunity to develop an operational system for diagnosing the conditions of TAN in the active zone of high-power reactor installations. For the conditions of transient and emergency modes of nuclear power plants with VVER, the thermodynamic approach of determining the conditions for the occurrence of thermoacoustic instability of a non-equilibrium two-phase coolant is more justified. Based on the thermodynamic approach, the conditions of thermoacoustic instability of the coolant in the active zone of the reactor were obtained. They depend on the defining thermodynamic parameters – reactor power, coolant consumption, pressure and temperature of the coolant at the entrance and exit of the active zone. It was established that in the nominal operating mode of the reactor, the coolant is stable with respect to thermoacoustic fluctuations. Based on the analysis of the well-known resonance approach to modeling the conditions for the occurrence of thermoacoustic instability (on the example of a single condensing bubble), it was established that the resonance effects of the coincidence of the frequency of propagation of acoustic waves and the frequency of condensation of steam bubbles can be significant for relatively short channels (less than 1 m) at relatively low pressures. For the conditions of transient and emergency modes of nuclear power plants with VVER, the thermodynamic approach of determining the conditions for the occurrence of thermoacoustic instability of a non-equilibrium two-phase coolant, based on the regularities of the conditions for the occurrence of oscillatory processes during acoustic perturbations of the thermodynamic parameters of the coolant flow in the active zone of a nuclear reactor, is more justified.
References
2 Kovrizhkin Yu., Emelianenko E., Skalozubov V. The limits of safe operation of facilities in relation to thermoacoustic instability of the coolant in the core. Nuclear & Radiation Safety 1 (1998) 123-129. (Rus).
3 V. Diemienkov, O. Shugailo, M. Mustafin, M. Makarenko. Assessment of the integrity of the equipment and pipelines of the AS based on related calculations in ANSYS and RELAP CODE. Nuclear & Radiation Safety 3(87) (2020) 46-54.
4 G. Sharaevsky. Problems of increasing the reliability of the calculated determination of the heat transfer crisis in water-cooled reactors based on computer thermohydraulic codes. Nuclear & Radiation Safety 3(79) (2018) 46-54
5 A. Mazurok, J. Alekseev, A. Krushynskyy, A. Kornytskyi. Validation of the thermal-hydraulic model of the reactor plant with a detailed breakdown of the downcomer section for the analysis of thermal loads on the reactor pressure vessel Nuclear & Radiation Safety. 2012. No. 1(53). P. 16-21 .
6 B. Gryschenko, M. Polyanskyi, O. Sevbo, I. Semenyuk. Application of probabilistic methods for NPP safety analysis in the study of violations of the brittle strength of the reactor pressure vessel. Nuclear & Radiation Safety. 2013. № 1(57). P. 22—25.
7 Skalozubov V. et al. Water hammers in transonic modes of steam-liquid flows in NPP equipment. Nuclear & Radiation Safety 2(82) (2019) 46-49.
8 Skalozubov V.et al. Analysis of Reliability-Critical Hydraulic Impact Conditions at WWER-1000 NPP Active Safety Systems. Nuclear & Radiation Safety 1(81) (2019) 42-45.
9 Vyshemirskyi M., Mazurok A., Nosovsky A. Influence of initial and boundary conditions on the formation of reactor pressure vessel thermal shock. Nuclear & Radiation Safety 1(57) (2013) 26-30. (Rus).
10. Scientific and technical basis of measures to improve the safety of NPPs with VVER. Institute of NPP Safety Problems of the National Academy of Sciences of Ukraine. Under the editorship of Academician O. Klyuchnikova, Chernobyl. 2012, 296 с.
11. I. Sharaievskii, N. Fialko, A. Nosovsky, L. Zimin, G. Sharaievskii. Actual problems of thermal physics of design and severe accidents of nuclear power units. Nuclear & Radiation Safety №2(70) (2016) P. 32-36.
12. Sauvage E., Musoyan G. Nuclear Reactor Severe Accident Analysis: Applications and Management Guidelines. SARnet 17, Budapest, Hungary, April 1-11, 2008.
Abstract views: 252 PDF Downloads: 270
If the article is accepted for publication in the journal «Thermophysics and Thermal Power Engineering» the author must sign an agreementon transfer of copyright. The agreement is sent to the postal (original) or e-mail address (scanned copy) of the journal editions.



