EDN: JPCEXF
Authors & Affiliations
Perevezentsev V.V.
Bauman Moscow State Technical University (National Research University), Moscow, Russia
Perevezentsev V.V. – Professor, Associate Professor, Dr. Sci. (Tech.). Contacts: Bld. 1, block 5, 2d Baumanskaya st., Moscow, 105005. Tel.: +7(499) 263-60-73, +7 (916) 181-53-70; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Abstract
Vibration processes in nuclear reactors largely determine reliability of equipment and safety of operation of the power unit as a whole. One of the most important mechanical systems that determine the trouble-free operation of reactor plants (RF) with VVER is fuel assemblies (FA). The turbulent flow of the coolant initiates and maintains mechanical vibrations (vibrations) of both individual fuel rods and the fuel bundle as a whole. Vibrations of fuel rods contribute to the origin and development of damage to the cladding up to the formation of through defects with the release of radioactive fission products into a coolant. The intensity of vibrations is determined by the hydrodynamic loads on the streamlined surfaces and the flexural stiffness of the beam as a whole or individual fuel rods. Therefore, the improvement of design solutions from the standpoint of the vibration strength of fuel assemblies is possible if there is a quantitative relationship between the intensity of vibrations and the acting hydrodynamic loads and flexural stiffness of the structure. Hydrodynamic loads are obtained on the basis of multipoint measurements of pressure pulsations by piezoresistive sensors in two cross-sections along the length of the fuel rod beam. At the same time, the levels of vibrations (deflections of the fuel bundle) were simultaneously measured in the same cross-sections using piezoresistive two-component vibroaccelerometers as part of measuring channels with integrating amplifiers. To increase the vibration strength of the fuel bundle and the FA design, it is necessary to both increase the flexural rigidity and reduce hydrodynamic disturbances (pressure pulsations) at the entrance to the fuel bundle. To increase the vibration strength of the fuel bundle and the FA design, it is necessary to both increase the flexural rigidity and reduce hydrodynamic disturbances (pressure pulsations) at the entrance to the fuel bundle. The study of the mechanisms of fuel rod vibration excitation, the determination of hydrodynamic loads distributed along their length will make it possible to develop design solutions aimed at reducing pressure pulsations at the inlet to the VVER FA in order to reduce the intensity of fuel rod vibrations. Experimental studies of vibrations of fuel rod beams were carried out on a hydrodynamic bench using a full-scale model of the second-generation VVER-440 fuel assemblies with lead simulators of fuel pellets. Generalizing experimental data on dimensionless vibration displacements of the fuel bundle depending on dimensionless hydrodynamic loads were obtained. The established ratios are used for quantitative comparative estimates of the vibration intensity of fuel rod beams of different VVER fuel assemblies.
Keywords
VVER FA, fuel rods, turbulent coolant flow, hydrodynamic excitation of vibrations, pressure pulsations, intensity of vibrations of fuel rods
Article Text (PDF, in Russian)
References
- Panyushkin A.K., Potoskaev G.G., Kurskov V.S., Bek E.G., Solonin V.I., Krapivtsev V.G., Perevezentsev V.V., Rekshnya N.F., Stolotnyuk S.V., Getya S.I., Matveev A.N., Kutychkin S.G., Prus V.V. Stend dlya eksperimental'nykh issledovaniy gidrodinamicheskikh i vibratsionnykh protsessov v TVS VVER-440. Nauchnyye issledovaniya v oblasti yadernoy energetiki v tekhnicheskikh vuzakh Rossii. Sb. st. [Stand for experimental studies of hydrodynamic and vibrational processes in VVER-440 fuel assemblies. Scientific Research in the Field of Nuclear Power Engineering in Technical Universities of Russia]. Moscow, Izd-vo MEI Publ., 1999. P. 59.
- Panyushkin A.K., Potoskaev G.G., Kurskov V.S., Bek E.G., Solonin V.I., Krapivtsev V.G., Perevezentsev V.V., Rekshnya N.F., Stolotnyuk S.V., Getya S.I., Matveev A.N., Kutychkin S.G., Prus V.V. Eksperimental'nyye issledovaniya gidrodinamicheskogo vozdeystviya potoka teplonositelya na konstruktivnyye elementy TVS VVER-440. Nauchnyye issledovaniya v oblasti yadernoy energetiki v tekhnicheskikh vuzakh Rossii. Sb. st. [Experimental studies of the hydrodynamic impact of the coolant flow on the structural elements of VVER-440 fuel assemblies. Scientific Research in the Field of Nuclear Power Engineering in Technical Universities of Russia]. Moscow, Izd-vo MEI Publ., 1999. P. 63.
- Perevezentsev V.V. Vozbuzhdeniye kolebaniy puchka tvelov reaktorov VVER turbulentnym potokom teplonositelya [Excitation of vibrations of the fuel beam of VVER reactors by turbulent coolant flow]. Vestnik MGTU im. N.E. Baumana. Seriya: Mashinostroyeniye – Herald of Bauman Moscow State Technical University. Series: Mechanical Engineering, 2009, no. 4, p. 78. EDN: KZMOSF.
- Perevezentsev V.V., Solonin V.I. Nestatsionarnyye gidrodinamicheskiye nagruzki i vibratsii puchka tvelov v TVS VVER-440 [Nonstationary hydrodynamic loads and vibrations of a fuel rod bundle in VVER-440 fuel assemblies]. Izvestiya vuzov. Yadernaya energetika, 2022, no. 2, p. 141. EDN: JWBKHZ.
- Perevezentsev V.V., Solonin V.I. Eksperimental'noye issledovaniye gidrodinamicheskogo vozbuzhdeniya vibratsiy tvelov v TVS VVER-440 [Experimental study of hydrodynamic excitation of fuel rods vibrations in fuel assembly of WWER-440]. Voprosy atomnoy nauki i tekhniki. Seriya: Yaderno-reaktornyye konstanty – Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2022, no. 2, p. 141. EDN: EIJKGI.
- Solonin V.I., Perevezentsev V.V. Vliyaniye gidrodinamicheskikh nagruzok na vibratsii puchkov tvelov teplovydelyayushchikh sborok reaktorov tipa VVER [Influence of hydrodynamic loads on the vibrations of fuel rod bundles of fuel assemblies of VVER reactors]. Problemy mashinostroyeniya i nadezhnosti mashin – Problems of Mechanical Engineering and Reliability of Machines, 2009, no. 4, p. 92. EDN: KUGQOD.
- Prochnost', ustoychivost', kolebaniya. Spravochnik. V trekh tomakh. Pod red. I.A. Birgera, Ya.G. Panovko [Strength, stability, vibrations. Handbook. In three volumes. Ed. by I.A. Birger, Ya.G. Panovko]. Moscow, Mashinostroyeniye Publ., 1988. Vol. 1. 831 p.
- Solonin V.I., Perevezentsev V.V. Studying the vibration and random hydrodynamic loads on the fuel rods bundles in the fuel assemblies of the reactor installations used at nuclear power stations equipped with VVER reactors. Therm. Eng., 2012, vol. 59, pp. 384–389. DOI: https://doi.org/10.1134/S0040601512050114. EDN: OWXCFD.
- Logvinov S.A., Bezrukov Yu.A., Dragunov Yu.G. Eksperimental'noye obosnovaniye teplogidravlicheskoy nadezhnosti reaktorov VVER [Experimental substantiation of thermohydraulic reliability of VVER reactors]. Moscow, IKTs Akademkniga Publ., 2004. 255 p. ISBN: 5-94628-182-8. EDN: QMIGLL.
- Makarov V.V., Afanasyev A.V., Matvienko I.V. Modal'nyy analiz maketov TVS reaktorov VVER pri silovom i kinematicheskom vozbuzhdenii vibratsii [Modal analysis of models of fuel assemblies of VVER reactors at power and kinematic excitation of vibration]. Sb. dokladov 5-y mezhdunar. nauch.-tekhn. konferentsii “Obespecheniye bezopasnosti AES s VVER” [Proc. of 5th International. Scientific and Technical Conf.]. Podolsk, 2007, vol. 2, p. 137.
UDC 621.039.546.8
Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2025, no. 1, 1:16
