EDN: YHJJPS
Authors & Affiliations
Sorokin A.P.1, Kuzina Yu.A.1, Denisova N.A.1, Sorokin G.A.2
1 A.I. Leypunsky Institute for Physics and Power Engineering, Obninsk, Russia
2 Moscow Institute of Physics and Technology (National Research University), Moscow, Russia
Sorokin A.P.1 – Chief Researcher, Dr. Sci. (Tech.). Contacts: 1, pl. Bondarenko, Obninsk, Kaluga region, 249033. Tel.: +7 (905) 641-20-99; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Kuzina Yu.A.1 – Head of the Nuclear Power Department, Cand. Sci. (Tech.).
Denisova N.A.1 – Lead Engineer.
Sorokin G.A.2 – Associate Professor, Cand. Sci. (Tech.).
Abstract
The results of a series of experiments carried out at JSC “SSC RF – IPPE” on heat exchange and circulation stability during boiling of a sodium-potassium alloy on models of single fuel assemblies and in a system of parallel fuel assemblies are presented, taking into account the influence of various factors on the boiling process in the natural convection mode. The data obtained showed that the regime of stable nucleate boiling is observed only in a limited region of heat flows; its transition to the regime of unstable pulsating slug boiling is determined by various factors. The boundaries of the transition from bubble to slug, dispersed-ring and dispersed flow regiones of a two-phase flow of liquid metal in a fuel assembly are approximated by simple dependencies. The occurrence of an oscillatory process during boiling of the coolant in one of the parallel fuel assemblies leads to an antiphase oscillatory process in the other fuel assembly; subsequently, oscillations in different circuits are of an antiphase nature. Hydrodynamic interaction of circuits can lead to a significant increase in the amplitude of fluctuations in coolant flow in them, “resonance” of flow pulsations, possible “locking” or inversion of coolant flow in the circuits, an increase in the temperature of the coolant and fuel rod cladding (the effect of interchannel instability) and a heat transfer crisis. The experimentally discovered effect of the influence of fuel rod surface roughness on heat transfer and flow regimes during boiling of liquid metal in fuel rod assemblies is demonstrated. The results of experiments on heat transfer during sodium boiling in natural and forced convection regimes in a fuel assembly model with a “sodium cavity” located above the reactor core show that it is possible for long-term cooling of fuel elements in a fuel assembly with sodium for these conditions. The results of analysis and generalization of data on and cartogram of two-phase flow regimes and heat transfer during boiling of alkali liquid metals in fuel rod assemblies of fast reactors are presented. The possibility of modeling heat transfer and circulation stability during boiling of alkali liquid metals both in single fuel assemblies and in a system of parallel fuel assemblies in circuits with natural coolant circulation using a channel-by-channel model of thermo-hydraulic calculation of two-phase flows with phase separation is demonstrated. The results of comparison of data from computational and experimental studies are presented.
Keywords
fast neutron reactor, fuel assembly, experiment, numerical modeling, alkali liquid metals, hydrodynamics, heat transfer, boiling, circulation stability, interchannel instability, heat transfer, heat transfer crisis, regime map, two-phase flow regimes
Article Text (PDF, in Russian)
References
- Bagdasarov Yu.E., Kuznetsov I.A. Nonsteady and emergency conditions of fast-reactor operation and their role in safety systems. At Energy, 1982, vol.52, issue 1, pp. 1–9. DOI: https://doi.org/10.1007/BF01121765.
- Sorokin G.A., Avdeev E.F., Zhukov A.V., Bogoslovskaya G.P., Sorokin A.P. Development of thermohydraulics codes for modeling liquid metal boiling in LMR fuel subassemblies. IAEA-TECDOC-1157, LMFR core thermohydraulics: Status and prospects, June 2000, pp. 107–126.
- Ashurko Yu.M., Andreeva K.A., Burevsky I.V., Volkov A.V., Eliseev V.A., Egorov A.V., Kuznetsov I.A., Korobeynikova L.V., Matveev V.I., Solomonova N.V., Khomyakov Yu.S., Tsarapkina A.N. Investigation of the SVRE influence on the safety of large size sodium fast reactor. Izvestiya vuzov. Yadernaya Energetika, 2014, no. 3, pp. 5–13.
- Ashurko Yu.M., Volkov A.V., Raskach K.F. et al. Neutron-Physical Model Impact on the Calculation of a Serious Accident with Sodium Boiling in a Fast Reactor. At Energy, 2017, vol.122, issue 4, pp. 217–225. DOI: https://doi.org/10.1007/s10512-017-0259-3.
- Sorokin G.A., Sorokin A.P. Experimental and Numerical Investigations of Liquid Metal Boiling in Fuel Subassemblies under Natural Circulation Conditions. Proceeding of the First COE-INES International Symposium, INES-1. October 31 – November 4, 2004, Tokyo, Japan. 2005. The Progress in Nuclear Energy Journal, 2005, Special Issue: Innovative Nuclear Energy System for Sustainable Development of the World. vol. 47, no. 1–4, pp. 656–663.
- Kutateladze S.S., Borishansky V.M., Novikov I.I., Fedynsky O.S. Teploperedacha v zhidkikh metallakh. Zhidkometallicheskiye teplonositeli [Heat transfer in liquid metals. Liquid metal coolants]. Moscow, Atomizdat Publ., 1958. 414 p.
- Kirillov P.L. Teploobmen zhidkikh metallov v kruglykh trubakh (odnofaznyy i dvukhfaznyy potoki). Diss. dokt. tekh. nauk [Heat transfer of liquid metals in round pipes (single-phase and two-phase flows). Dr. tech. sci. diss.]. Moscow, IVTAN Publ., 1968.
- Subbotin V.I., Sorokin D.N., Ovechkin D.M., Kudryavtsev A.P. Teploobmen pri kipenii zhidkikh metallov v usloviyakh yestestvennoy konvektsii [Heat transfer during boiling of liquid metals under conditions of natural convection]. Moscow, Nauka Publ., 1969. 208 p.
- Borishansky V.M., Kutateladze S.S., Novikov I.I., Fedynsky O.S. Zhidkometallicheskiye teplonositeli [Liquid metal coolants]. Moscow, Atomizdat Publ., 1976. 328 p.
- Dwyer O.E. Boiling Liquid-Metal Heat Transfer. American Nuclear Society, 1976. 446 p.
- Zeigarnik Yu.A., Litvinov V.D. Kipeniye shchelochnykh metallov v kanalakh [Boiling of alkali metals in channels]. Moscow, Nauka Publ., 1983. 125 p.
- Kottowski H.M., Savateri C. Evaluation of Sodium Incident Overheat Measurements with Regard to the Importance of Experimental and Physical Parameters. International Journal of Heat and Mass Transfer, 1977, vol. 20, no. 42, pp. 1281–1300.
- Kikuchi Y., Takahushi T., Haga K. Incipient Boiling of Sodium in Single-Pin Annular Channel. Journal of Nuclear Science and Technology, 1974, vol. 11, no. 5, pp. 172–186.
- Kikuchi Y., Haga K., Takahashi T. Experimental Study of Steady State Boiling of Sodium Flowing in a Single-Pin Annular Channel. Journal of Nuclear Science and Technology, 1975, vol. 12, no. 2, pp. 83–91.
- Kikuchi Y. Transient Boiling of Sodium in Seven Pin Bundle under Loss of Flow Conditions. Journal of Nuclear Science and Technology, 1978, vol. 15, no. 9, pp. 658–667.
- Kikuchi Y., Daigo Y., Ohtsubo A. Incipient Boiling of Sodium in Seven-Pin Bundle under Forced Convection Conditions. Journal of Nuclear Science and Technology, 1978, vol. 15, no. 7, pp. 533–542.
- Kikuchi Y. Boiling in 19-Pin Bundle under Loss-of-Flow Conditions in Local Blockage. Nuclear Engineering and Technology, 1981, vol. 66, no. 5, pp. 357–366.
- Wantland J.L. et al. Dynamic Boiling in a 19-Pin Simulated LMFBR Fuel Assembly. Transactions of the American Nuclear Society, 1977, vol. 27, pp. 567–569.
- Huber F. Loss of Flow Experiments in Sodium in an Electrically Heated 37-Pin Bundle with Sinusoidal Axial Heat Flux Distribution. Proceeding of the LMFBR Safety Topical Meeting. Lion – Ecullu, France, 1982, pp. 341–349.
- Huber F., Peppler W. Boiling and Dryout behind Local Blockages in Sodium Cooled Rod Bundles. Nuclear Engineering and Design, 1984, vol. 82, no. 1–3, pp. 341–363.
- Seiler J.M. Studies of Sodium Boiling Phenomena in Out of Pile Rod Bundles for Various Accidental Situations in LMFBR: Experiments and Interpretation. Nuclear Engineering and Design, 1982, vol. 82, no. 1–3, pp. 227–239.
- Seiler J.M., Cognet Y., Leborgue E. et al. French LMFBR Core Thermal Hydraulic Studies for Nominal and Accident Conditions. Nuclear Engineering and Design, 1990, vol. 124, no. 3, pp. 403–416.
- Huber F., Kaizer A., Mattes K. et al. Steady State and Transient Sodium Boiling in a 37-Pin Bundle. Nuclear Engineering and Design, 1987, vol. 100, no. 3, pp. 377–386.
- Kaizer A., Huber F. Sodium Boiling Experimental a Low Power under Natural Convection. Nuclear Engineering and Design, 1987, vol. 100, no. 3, pp. 367–376.
- Yamaguchi K. Flow Pattern and Dryout under Sodium Boiling Conditions. Nuclear Engineering and Design, 1987, vol. 99, no. 3, pp. 247–263.
- Haga K. Temperature Rise due to Fission gas Release in Locally Blocked LMFBR Subassembly Simulators. Proceedings of the LMFBR Safety Topical Meeting. Lion – Ecully, France, July 19–23, 1982, pp. 291–300.
- Votani M., Haga K. Experimental Investigation of Sodium Boiling in Partially Blocked Fuel Subassemblies. Nuclear Engineering and Design, 1984, vol. 82, no. 3, pp. 319–328.
- Kaizer A., Huber F., Bottoni M., Dorr B. Contribution to Sodium Boiling Heat Transfer, Pressure Drop and Void Distributions In Multi-pin geometry. of NURETH-IV. Karlsruhe, Germany, 1989, vol. 1, pp. 610–616.
- Yamaguchi K., Nakamura H., Haga K. Boiling and Dryout Condition in Disturbed Cluster Geometry and Their Applications to the LMFBR Local Fault Assessment. Nuclear Science and Engineering, 1984, vol. 3, pp. 464–474.
- Bergeonneau P., Rameau B. Conditions for Locally Stable Boiling in a Pin Bundle. Science and Technology Fast Reactor Safety, BNES. London, 1986, pp. 445–456.
- Zhukov A.V., Sorokin A.P., Khudasko V.V. Vliyaniye teplogidravlicheskikh faktorov na bezopasnost' TVS reaktorov. Uchebnoye posobiye [Influence of thermal-hydraulic factors on the safety of reactor fuel assemblies. Textbook]. Obninsk, Institute of Atomic Energy Publ., 1990. 82 p.
- Sorokin A.P., Efanov A.D., Ivanov E.F., Martsinyuk D.E., Bogoslovskaya G.P., Rymkevich K.S., Malkov V.L. Raschetno-eksperimental'nyye issledovaniya usloviy ustoychivogo teploobmena pri vozniknovenii kipeniya zhidkogo metalla v rezhime avariynogo raskholazhivaniya bystrogo reaktora [Calculation and experimental studies of the conditions of stable heat transfer when boiling of liquid metal occurs in the emergency cooling mode of a fast reactor]. Izvestiya vuzov. Yadernaya energetika – News of universities. Nuclear energy, 1999, no. 2, pp. 59–70.
- Sorokin A.P., Efanov A.D., Ivanov E.F. et al. Heat transfer during boiling of a liquid metal during emergency cooldown of a fast-neutron reactor. At Energy, 1999, vol. 87, issue 5, pp. 801–807. DOI: https://doi.org/10.1007/BF02673277.
- Efanov A.D., Sorokin A.P., Ivanov Eu.F., Bogoslovskaya G.P., Kolesnik V.P., Martsinyuk S.S., Sorokin G.A., Rymkevich K.S. An investigation of the heat transfer and stability of liquid-metal coolant boiling in a natural circulation circuit. Thermal Engineering, 2003, vol. 50, no. 3, pp. 194–201.
- Efanov A.D., Sorokin A.P., Ivanov Eu.F., Bogoslovskaya G.P., Ivanov V.V., Volkov A.D. Liquid-metal boiling heat transfer in a system of channels under natural circulation conditions. of the 11 International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-11). Avignon, France, October 2–6, 2005.
- Efanov A.D., Sorokin A.P., Ivanov E.F., Sorokin G.A., Bogoslovskaia G.P., Ivanov V.V., Volkov A.D., Sorokin G.A., Zueva I.R., Fedosova M.A. Heat transfer under natural convection of liquid metal during its boiling in a system of channels. Eng, 2007, vol. 54, no. 3, pp. 214–222. DOI:https://doi.org/10.1134/S0040601507030081.
- Sorokin A.P., Kuzina Yu.A., Ivanov E.F. Teploobmen pri kipenii zhidkometallicheskikh teplonositeley v TVS bystrykh reaktorov v avariynykh rezhimakh [Heat transfer at boiling of liquid metallic coolants in fuel assemblies of fast reactors under emergency conditions]. Voprosy atomnoy nauki i tekhniki. Seriya: Yaderno-reaktornyye konstanty – Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2018, no. 3, pp. 176–194. Available at: https://vant.ippe.ru/en/year2018/3/thermal-physics-hydrodynamics/1527-17.html (accessed 31.01.2024).
- Sorokin G.A., Ninokata H., Sorokin A.P., Endo H., Ivanov Eu.F. Numerical Study of Liquid Metal Boiling in the System of Parallel Bundles under Natural Circulation. Journal of Nuclear Science and Technology, 2006, vol. 43, no. 6, pp. 623–634.
- Volkov A.V., Kuznetsov I.A. Usovershenstvovannaya model' kipeniya natriya dlya analiza avariy v bystrom reaktore [An improved sodium boiling model for fast reactor accident analysis.]. Izvestiya vuzov. Yadernaya energetika – News of universities. Nuclear energy, 2006, no. 2, pp. 101–111.
- Kasahara F., Ninokata H., Sorokin A.P., Bogoslovskaya G.P. Analysis of liquid-metal boiling under the natural circulation condition. of the NTHAS2: Second Japan – Korea Symposium on Nuclear Thermal Hydraulics and Safety. Fukuoka, Japan, October 15–18, 2000.
- Sorokin G.A., Ninokata H., Endo H., Efanov A.D., Sorokin A.P., Ivanov E.F., Bogoslovskaya G.P., Volkov A.D., Zueva I.R. Eksperimental'noye i raschotnoye modelirovaniye teploobmena pri kipenii zhidkogo metalla v sisteme parallel'nykh teplovydelyayushchikh sborok v rezhime yestestvennoy konvektsii [Experimental and computational modeling of heat transfer during boiling of liquid metal in a system of parallel fuel assemblies in the natural convection mode]. Izvestiya vuzov. Yadernaya energetika – News of universities. Nuclear energy, 2005, no. 4, pp. 92–106.
- Borishanskii V.M., Andreevskii A.A., Zhokhov K.A. et al. Heat emission from potassium boiling in a tube in the region of moderate vapor content. At Energy, 1966, vol. 21, issue 1, pp. 687–689. DOI: https://doi.org/10.1007/BF01134270.
- Alad'ev R.T., Gorlov I.G., Dodonov L.D. et al. Teploobmen pri kipenii kaliya v trubakh s ravnomernym teplopodvodom [Heat exchange during boiling of potassium in pipes with uniform heat supply]. Izvestiya AN SSSR. Energetika i transport – Proceedings of the USSR Academy of Sciences. Energy and transport, 1966, no. 2, p. 136.
- Grachev N.S., Zelinsky V.N., Kirillov P.L., Subbotin V.I., Turchin N.M. Teploobmen i Gidrodinamika pri kipenii kaliya v trubakh [Heat transfer and hydrodynamics during potassium boiling in pipes]. Teplofizika Vysokikh Temperatur – High Temperature, 1968, vol. 6, no. 4, pp. 682–690.
- Kirillov P.L. Databank on heat transfer in liquid metals. Part 2. Heat transfer during boiling of liquid metals: Preprint FEI-3276 – Preprint IPPE-3276. Obninsk: IPPE, 2017. 40 p.
- Zeigarnik Yu.A., Kirillov P.L., Ushakov P.A., Ivanovsky M.N. Teploobmen zhidkikh metallov pri kipenii i kondensatsii [Heat transfer of liquid metals during boiling and condensation]. Teploenergetika – Thermal engineering, 2001, no. 3, pp. 2–8.
- Zeigarnick Yu.A., Litvinov V.D. Heat transfer and Pressure Drop in Sodium Boiling in Tubes. Nuclear Science and Engineering, 1980, vol. 73, no. 1, pp. 19–28.
- Aladiev L.T., Gorlov I.G., Dodonov L.D. Potassium Boiling Heat Transfer in Tubes with Uniform Heat Flux. Investigations of Heat Transfer, Hydrodynamics and Material Thermophysical Properties. Moscow: Nauka Publ., 1968.
- Wallis G.B. One-Dimensional Two-Phase Flow. McGraw Hill, 1969. 408 p.
- Yagov V.V. Teploobmen v odnofaznykh sredakh i pri fazovykh prevrashcheniyakh: uchebnoye posobiye dlya vuzov [Heat transfer in single-phase media and during phase transformations: a textbook for universities]. : Izdatel'skiy dom MEI Publ., 2014. 542 p.
- Gogonin I.I. The dependence of boiling heat transfer on the properties and geometric parameters of heat-transfer wall. High Temp., 2006, vol. 44, issue 6, pp. 913–921. DOI: https://doi.org/10.1007/s10740-006-0110-3.
- Grigoriev V.A., Pavlov Yu.M., Ametistov E.V. Kipeniye kriogennykh zhidkostey [Boiling of cryogenic liquids]. Moscow, Energiya Publ., 289 p.
- Galin N.M., Kirillov P.L. Teplomassoobmen (v yadernoy energetike) [Heat and mass transfer (in nuclear energy)]. Moscow, Energoatomizdat Publ., 1987. 289 p.
- Prisnyakov V.F. Kipeniye [Boiling]. Kyiv, Naukova Dumka Publ., 1988. 240 p.
- Teplofizicheskaya stendovaya baza atomnoy energetiki Rossii i Kazakhstana [Thermophysical bench base of nuclear power in Russia and Kazakhstan. Ed. Pershukov V.A., Arkhangelsky N.V., Kononov O.E., Sorokin A.P.]. Sarov, FSUE “RFNC – VNIIEF” Publ., 2016. 160 p.
- Sorokin A.P., Kuzina Yu.A., Ivanov E.F. Characteristics of Heat Transfer during Boiling of Liquid Metal in the Fuel Assemblies of Fast Reactors in Emergency Regimes. At Energy, 2019, vol. 126, issue 2, pp. 73–82. DOI: https://doi.org/10.1007/s10512-019-00518-0.
- Sorokin A.P., Ivanov E.F., Malkov V.L., Kolesnik V.P., Martsinyuk D.E., Rymkevich K.S., Korkhov O.A. Eksperimental'nyye issledovaniya teploobmena i ustoychivosti kipeniya zhidkometallicheskogo teplonositelya v konture yestestvennoy tsirkulyatsii [Experimental studies of heat transfer and stability of boiling liquid-metal coolant in a natural circulation circuit]. Preprint FEI-2631 – Preprint IPPE-2631. Obninsk: IPPE, 1997. 32 p.
- Sorokin A.P., Ivanov E.F., Bogoslovskaya G.P., Martsinyuk D.E., Kolesnik V.P., Malkov V.G., Rymkevich K.S. Boiling of Liquid Metal in Natural Circulation Loop. of 11th International Heat Transfer Conference. Kyongju, Korea, August 23–28, 1998, vol. 2, pp. 357–361.
- Aritomi M., Chiang J.H., Nakahashi T., Wataru M., Mori M. Fundamental Study on Thermo-Hydraulics during Stop-Up in Natural Circulation Boiling Water Reactor, (I) Thermo-Hydraulics Instabilities. Nuclear Science and Technology, 1992, vol. 29, no. 7, pp. 631–661.
- Chiang J.H., Aritomi M. Fundamental Study on Thermo-Hydraulics during Stop-Up in Natural Circulation Boiling Water Reactor, (II) Natural Circulation Oscilation Induced by Hydrostatic Head Fluctuation. Nuclear Science and Technology, 1993, vol. 30, no. 3, pp. 203–211.
- Хабенский В.Б., Герлига В.А. Нестабильность потока теплоносителя в элементах оборудования. Saint Petersburg: Nauka Publ., 1994.
- Podowski M.Z., Rosa M.P. Modeling and Numerical Simulation of Oscillatory Two-phase Flows with Application to Boiling Water Nuclear Reactors. Nuclear Engineering and Design, 1997, vol. 177, no. 2, pp. 179–184.
- Zanocco P., Gimenez M., Delmastro D. Modeling Aspects in Linear Stability Analysis of a Self-Pressurized, Natural Circulation Integral Reactor. Nuclear Engineering and Design, 2004, vol. 231, no. 3, pp. 283–301.
- Koncoro H., Iwahashi K., Rao Y.F., Fukuda K. Experimental Study on the Stability Characteristics of Two-phase Flows in Parallel Boiling Channels under Natural-Circulation Conditions. International Conference on Nuclear Engineering, ASME, 1996, vol. 1, Part 1, pp. 373–383.
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