Sorokin A.P., Kuzina Ju.A., Ivanov E.F.
A.I. Leypunsky Institute for Physics and Power Engineering, Obninsk, Russia
The solution of the problem of cooling fuel rods in the fuel assemblies of the core in emergency conditions, such as ULOF, causes the study of heat transfer during boiling of liquid metal coolants at reduced coolant flow rates or even overturning of circulation in fuel assemblies. There are only limited data about sodium boiling in bundles of fuel rods for regimes with low flow velocities of the coolant or natural convection. The results of a series of experiments on the boiling of sodium-potassium alloy in models of single fuel assemblies and in a system of parallel fuel assemblies in circuits with natural circulation carried out in JSC “SSC RF-IPPE” are presented. Also the results of experimental studies of heat transfer in the boiling of sodium in the FA model with a "sodium cavity" located above the reactor core in modes with natural and forced convection are presented. It was shown for the first time that in the presence of a "sodium cavity" in a fuel assembly designed to compensate for the positive sodium void reactivity effect in fast reactors under emergency situations with sodium boiling, it is possible to continuously cooling the fuel elements in fuel assemblies. The problems of further research are discussed.
1. Kutateladze S.S., Borishanskiy V.M., Novikov I.I., Fedynskiy O.S. Teploperedacha v zhidkikh metallakh. Zhidkometallicheskie teplonositeli [Heat transfer in liquid metals. Liquid metal coolants]. Moscow, Atomizdat Publ., 1958.
2. Subbotin V.I., Sorokin D.N., Ovechkin D.M., Kudryavtsev A.P. Teploobmen pri kipenii metallov v usloviyakh estestvennoy konvektsii [Heat transfer at boiling of metals under conditions of natural convection]. Moscow, Nauka, 1969.
3. Zeygarnik Yu.A., Litvinov V.D. Kipenie shchelochnykh metallov v kanalakh [The boiling of alkali metals in the channels]. Moscow, Nauka Publ., 1983.
4. Kirillov P.L. Teploobmen pri kipenii zhidkikh metallov v kruglykh trubakh (odnofaznyy i dvukhfaznyy potoki). Dis. dok. tekh. nauk [Heat transfer at boiling of liquid metals in round pipes (single-phase and two-phase flows). Dr. tech. sci. diss.]. Moscow, 1968.
5. Borishanskiy V.M., Kutateladze S.S., Novikov I.I., Fedynskiy O.S. Zhidkometallicheskie teplonositeli [Liquid metal coolants]. Moscow, Atomizdat Publ., 1976.
6. Dvayer O. Teploobmen pri kipenii zhidkikh metallov [Heat transfer at boiling of liquid metals]. Moscow, Mir Publ., 1980.
7. Kikuchi Y., Haga K. Sodium boiling experiments in a 19 pin bundle under loss-of-flow conditions. Nuclear Engineering and Design, 1981, vol. 66, pp. 357–366.
8. Haga K. Loss of flow experiment in a 37 pin bundle LMRBR fuel assembly. Nuclear Engineering and Design, 1984, vol. 82, pp. 305–318.
9. Yamaguchi K. Flow pattern and dryout under sodium boiling conditions at decay power levels. Nuclear Engineering and Design, 1987, vol. 99, no. 3, pp. 247–263.
10. Kaiser A., Peppler W. Flow rundown experiments in a seven pin bundle. Nuclear Engineering and Design, 1977, vol. 43, pp. 273–283.
11. Huber F., Peppler W. Boiling and dryout behind local blockages in sodium cooled rod bundles. Nuclear Engineering and Design, 1984, vol. 82, pp. 341–363.
12. Kaiser A., Huber F. Sodium boiling experiments at low power under natural convection conditions. Nuclear Engineering and Design, 1987, vol. 100, pp. 367–376.
13. Huber F., Kaiser A., Mattes K. and Peppler W. Steady state and transient sodium boiling experiments in a 37 pin bundle. Nuclear Engineering and Design, 1987, vol. 100, pp. 377–386.
14. Gnadt P.A., Carbajo J.J., Dearing J.F Sodium boiling experiments in the THORS facility. Nuclear Engineering and Design, 1984, vol. 82, pp. 241–280.
15. Seiler J.M. Studies on sodium boiling phenomena in out-of-pile rod bundles for various accidental situation in LMFBR: experiments and interpretations. Nuclear Engineering and Design, 1986, vol. 82, pp. 227–239.
16. Seiler J.M., Juhel D., Dufour Ph. Sodium boiling stabilization in a fast breeder subassembly during an unprotected loss of flow accident. Nuclear Engineering and Design, 2010, vol. 240, pp. 3329–3335.
17. Zhukov A.V., Sorokin A.P., Kornienko Yu.N. Metody i rezul'taty teplogidravlicheskikh issledovaniy nestatsionarnykh protsessov v TVS bystrykh reaktorov [Methods and results of thermohydraulic studies of nonstationary processes in fuel assemblies of fast reactors]. Obninsk, IPPE, 1988.
18. Sorokin A.P., Efanov A.D, Ivanov E.F., Martsinyuk D.E., Bogoslovskaya G.P., Rymkevich K.S., Mal'kov V.L. Raschetno-eksperimental'nye issledovaniya usloviy ustoychivogo teploobmena pri vozniknovenii kipeniya zhidkogo metalla v rezhime avariynogo raskholazhivaniya bystrogo reaktora [Calculation and experimental studies of the conditions for stable heat exchange in the boiling of liquid metal in the emergency cooling of a fast reactor]. Yadernaya energetika - Nuclear energy, 1999, no. 2, pp. 59–70.
19. Sorokin A.P., Efanov A.D., Ivanov E.F., Martsinyuk D.E., Bogoslovskaya G.P., Rymkevich K.S., Mal'kov V.L. Teploobmen pri kipenii zhidkogo metalla v rezhime avariynogo raskholazhivaniya bystrogo reaktora [Heat transfer at the boiling of liquid metal in the regime of emergency cooling of the fast reactor]. Atomnaya energiya - Atomic Energy, 1999, vol. 87, no. 5, pp. 337–342.
20. Efanov A.D., Sorokin A.P., Ivanov E.F., Bogoslovskaya G.P., Kolesnik V.P., Martsinyuk S.S., Mal'kov V.L., Sorokin G.A., Rymkevich K.S. Issledovaniya teploobmena i ustoychivosti kipeniya zhidkometallicheskogo teplonositelya v konture estestvennoy tsirkulyatsii [Studies of heat transfer and stability of boiling liquid metal coolant in the natural circulation circuit]. Teploenergetika - Thermal Engineering, 2003, no. 3, pp. 20–26.
21. 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.
22. 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. Proc. 11th Int. Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-11). Avignon, France, 2005.
23. Efanov A.D., Sorokin A.P., Ivanov E.F., Bogoslovskaya G.P., Ivanov V.V., Volkov A.D., Sorokin G.A., Zueva I.R. Teploobmen pri kipenii zhidkogo metalla v sisteme kanalov v rezhime estestvennoy tsirkulyatsii [Heat transfer at the boiling of liquid metal in the channel system in the regime of natural circulation]. Teploenergetika - Thermal Engineering, 2007, no. 3, pp. 43–51.
24. 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. Thermal Engineering, 2007, vol. 54, no. 3, pp. 214–222.
25. Kasahara F., Ninokata H., Sorokin A.P., Bogoslovskaya G.P. Analysis of liquid-metal boiling under the natural circulation condition. Proc. NTHAS2: Second Japan – Korea symposium on nuclear thermal hydraulics and safety. Fukuoka, Japan, 2000.
26. Sorokin G.A., Ninokata Kh., Endo Kh., Efanov A.D., Sorokin A.P., Ivanov E.F., Bogoslovskaya G.P., Volkov A.D., Zueva I.R. Eksperimental'noe i raschetnoe modelirovanie teploobmena pri kipenii zhidkogo metalla v sisteme parallel'nykh teplovydelyayushchikh sborok v rezhime estestvennoy konvektsii [Experimental and computational modeling of heat transfer in the boiling of liquid metal in a system of parallel fuel assemblies in the natural convection mode]. Izvestiya vuzov. Yadernaya energetika - Proseedings of Universities. Nuclear Power Engineering, 2005, no. 4, pp. 92–106.
27. Sorokin G.A., Sorokin A.P. Experimental and numerical investigations of liquid metal boiling in fuel subassemblies under natural circulation conditions. The Progress in Nuclear Energy Journal, 2005, vol. 47, no. 1–4, pp. 656–663.
28. 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.
29. Khafizov R.R., Poplavskiy V.M., Rachkov V.I., Sorokin A.P., Trufanov A.A., Ashurko Yu.M., Volkov A.V., Ivanov E.F., Privezentsev V.V. Eksperimental'nye issledovaniya teploobmena pri kipenii natriya v modeli TVS v obosnovanie bezopasnosti perspektivnogo reaktora na bystrykh neytronakh [Experimental studies of heat exchange in the boiling of sodium in the fuel assembly model in support of the safety of a prospective fast neutron reactor]. Teploenergetika - Thermal Engineering, 2017, no. 1, pp. 10–19.
30. Khafizov R.R., Poplavsky V.M., Rachkov V.I., Sorokin A.P., Trufanov A.A., Ashurko Yu.M., Volkov A.V., Ivanov E.F., Privezentsev V.V. Experimental studies of heat exchange for sodium boiling in the fuel assembly model: safety substantiation of a promising fast reactor. Thermal Engineering, 2017, vol. 64, no. 1, pp. 6–14.
31. 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.
32. 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.
33. Khabenskiy V.B., Gerliga V.A. Nestabil'nost' potoka teplonositelya v elementakh oborudovaniya [Instability of the coolant flow in the equipment elements]. St. Petersburg, Nauka Publ., 1994.
34. 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.
35. 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.
36. 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. Proc. Int. Conf. on Nuclear Engineering. ASME, 1996, vol. 1, no. 1, pp. 373–383.
37. Khafizov R.R., Ashurko Yu.M., Volkov A.V., Ivanov E.F., Privezentsev V.V., Sorokin A.P., Kumskoy V.V. Podgotovka eksperimental'nogo stenda AR-1 i eksperimental'noy modeli k provedeniyu issledovaniy kipeniya natriya v modeli TVS v obosnovanie bezopasnosti bystrogo reaktora novogo pokoleniya [Preparation of the experimental stand AP-1 and the experimental model for the study of boiling of sodium in the fuel assembly model in support of the safety of the fast reactor of the new generation]. Izvestiya vuzov. Yadernaya energetika - Proseedings of Universities. Nuclear Power Engineering, 2014, no. 1, pp. 77–87.
38. Ashurko Yu.M., Andreeva K.A., Bur'evskiy 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. Issledovanie vliyaniya natrievogo pustotnogo effekta reaktivnosti na bezopasnost' bystrogo natrievogo reaktora bol'shoy moshchnosti [nvestigation of the influence of sodium void reactivity effect on the safety of a fast sodium reactor of high power]. Izvestiya vuzov. Yadernaya energetika - Proseedings of Universities. Nuclear Power Engineering, 2014, no. 3, pp. 5–13.
