APPROACHES TO MODELING CONDITIONS OF THERMOACOUSTIC INSTABILITY IN NON-EQUILIBRIUM TWO-PHASE COOLANT OF NUCLEAR REACTORS
Abstract
The consequences of thermoacoustic instability of the coolant in the active zone of nuclear reactors can be high-amplitude, high-frequency dynamic loads on the internal structures and a violation of the tightness of the TVEL shells. However, until now, there are no reactor control/diagnostic systems and operational instructions for managing accidents in conditions of thermoacoustic instability of the coolant in the reactor core. The main reason for this situation is the lack of substantiated methods for modeling the criteria and conditions for the occurrence of thermoacoustic instability in the active zone. The purpose of the work is the development of a criterion method for modeling the conditions of thermoacoustic instability of the coolant in the active zone of the reactor to substantiate the appropriate reactor control systems and symptom-oriented emergency instructions. An original method of determining the criteria and conditions of thermoacoustic instability of the coolant in the active zone depending on the determining parameters of the thermodynamic state of the reactor plant has been developed.. Based on the thermodynamic approach, which takes into account the level of completion of interphase heat and mass transfer processes in acoustic pressure waves, the criteria and area of thermoacoustic instability of the coolant in the reactor core are determined. The established area of thermoacoustic instability of the coolant in the reactor core was verified on the basis of known experimental data obtained at the experimental installation, which meets the criteria of thermodynamic similarity to the core of the VVER-1000 core. Based on the developed criterion method, the main provisions and requirements for the relevant reactor control/diagnostic systems and symptom-oriented instructions for managing accidents in conditions of thermoacoustic instability of the coolant in the active zone of the reactors are defined.
References
2. Skalozubov V.I., Huiyu Zhou, Chulkin O.A., Pirkovskiy D.S. Modelling Method of Conditions for Reliability-Critical Hydraulic Impacts on Pumps of Thermal and Nuclear Power Plants. Problems of Atomic Science and Technology. 2017. No. 4(110). P. 74 – 78.
3. Skalozubov V., Bilous N., Pirkovskiy D. et al. Water Hammers in Transonic Modes of Steam-Liquid Flows in NPP Equipment. Nuclear and Radiation Safety. 2019. No. 2(82). P. 46 – 49.
4. Skalozubov V., Chulkin O., Pirkovskiy D. et al. Method for Determination of Water Hammer Conditions and Consequences in Pressurizers of Nuclear Reactors. Turkish Journal of Physics. 2019. V. 43, No. 3. Р. 229 – 235.
5. Antonyuk N., Gerliga V., Skalozubov V. Excitation of Thermoacoustic Oscillations in a Heated Channel. Journal of Engineering Physics and Thermophysics. 1990. V. 59, No. 4. Р. 1323 – 1328.
6. Komplex metodov pereotzenki bezopasnosty atomnoy energetiki Ukraine s uchetom ekologicheskih katastrof v Chernobyl i Fukushima [The complex of methods of reassessment of the safety of atomic energy of Ukraine taking into account the lessons of environmental disasters in Chernobyl and Fukushima] / Ed.V. Skalozubova Odessa: Astroprint, 2013. 244 p. (in Rus.)
Abstract views: 271 PDF Downloads: 323
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.



