Sorokin A.P.1, Ivanov Eu.F.1, Kuzina Ju.A.1, Denisova N.A.1, Nizovtsev A.A.1,
Privezentsev V.V.1, Sorokin G.A.2
1A.I. Leypunsky Institute for Physics and Power Engineering, Obninsk, Russia
2Moscow Institute of Physics and Technology, Moscow, Russia
Studies of the boiling of alkali metals show that, compared with boiling water, the process of boiling liquid metals has significant features. Cooling of a fuel assembly in accident conditions when accident protection is triggered and circulation pumps are switched off (ULOF) leads to the study of fuel elements cooling at reduced coolant flow rates or even tipping circulation in fuel assemblies. There is only limited data on the boiling of sodium in fuel assemblies in these regimes. The results of a series of experiments on heat transfer and stability of circulation during boiling of a sodiumpotassium alloy on single fuel assembly models and in a parallel fuel assembly system with natural coolant circulation performed at JSC “SSC RF — IPPE” are presented. The results of comparing the data of the calculated and experimental studies are presented. The influence of the surface roughness of the fuel rods on the heat transfer and flow regimes during boiling of a liquid metal in bundles is demonstrated. The results of experimental studies of heat transfer during boiling of sodium in natural and forced convection regimes in a fuel assembly model with a "sodium cavity" located above the reactor core intended to compensate for the positive sodium void reactivity effect in emergency situations with sodium boiling are also presented. It is shown that it is possible to provide continuous sodium cooling of fuel element simulators in fuel assemblies under these conditions. The results of the generalization of data on heat transfer during boiling of liquid metals in bundles and a cartogram of the regimes of two-phase flow during boiling of
liquid metals in bundles are presented. The objectives of further research are discussed.
1. Bagdasarov Yu.E., Kuznetsov I.A. Raschetnye issledovaniya nestatsionarnykh i avariynykh rezhimov raboty i ikh rol' v obespechenii bezopasnosti [Computational studies of non-stationary and emergency operating regimes and their role in ensuring safety. Atomnaya energiya – Atomic Energy, 1982, vol. 52, no. 1, pp. 3–10.
2. 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, 2000, pp. 107–126.
3. Ashurko Yu.M., Andreeva K.A., Buryevsky 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 [Investigation of the effect of the sodium void effect of reactivity on the safety of a fast high-power sodium reactor. Izvestiya vuzov. Yadernaya energetika – Proseedings of Universities. Nuclear Power Engineering, 2014, no. 3, pp. 5–13.
4. Ashurko Yu.M., Volkov A.V., Raskach K.F., Solomonova N.V. Vliyanie neytronno-fizicheskoy modeli na raschet tyazheloy avarii s kipeniem natriya v bystrom reaktore [The influence of the neutron-physical model on the calculation of a severe accident with boiling sodium in a fast reactor. Atomnaya energiya – Atomic Energy, 2017, vol. 122, no. 4, pp. 183–189.
5. 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. Special Issue: Innovative Nuclear Energy System for Sustainable Development of the World. Proceeding of the First COE-INES International Symposium, 2005, vol. 47, no. 1–4, pp. 656–663.
6. Kutateladze S.S., Borishansky V.M., Novikov I.I., Fedynsky O.S. Teploperedacha v zhidkikh metallakh. Zhidkometallicheskie teplonositeli [Heat transfer in liquid metals. Liquid metal coolants]. Moscow, Atomizdat Publ., 1958.
7. Kirillov P.L. Teploobmen zhidkikh metallov v kruglykh trubakh (odnofaznyy i dvukhfaznyy potoki). Diss.
dok. tekh. nauk [Heat transfer of liquid metals in round pipes (single-phase and two-phase flows). Dr. techn. Sci. diss.]. Moscow, 1968.
8. Subbotin V.I., Sorokin D.N., Ovechkin D.M., Kudryavtsev A.P. Teploobmen pri kipenii zhidkikh metallov v usloviyakh estestvennoy konvektsii [Heat transfer during boiling of liquid metals in conditions of natural convection]. Moscow, Science Publ., 1969. 208 p.
9. Borishansky V.M., Kutateladze S.S., Novikov I.I., Fedynsky O.S. Zhidkometallicheskie teplonositeli [Liquid metal coolants]. Moscow, Atomizdat Publ., 1976.
10. Dwyer O. Teploobmen pri kipenii zhidkikh metallov [Heat transfer during the boiling of liquid metals]. Moscow, Mir Publ., 1980. 516 p.
11. Zeigarnik Yu.A., Litvinov V.D. Kipenie shchelochnykh metallov v kanalakh [Boiling of alkali metals in channels]. Moscow, Science Publ., 1983. 125 p.
12. 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.
13. 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.
14. 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.
15. 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.
16. 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.
17. 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.
18. 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.
19. 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.
20. 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.
21. 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.
22. 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.
23. 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.
24. 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.
25. Yamaguchi K. Flow Pattern and Dryout under Sodium Boiling Conditions. Nuclear Engineering and Design, 1987, vol. 99, no. 3, pp. 247–263.
26. 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, 1982, pp. 291–300.
27. 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.
28. Kaizer A., Huber F., Bottoni M., Dorr B. Contribution to Sodium Boiling Heat Transfer, Pressure Drop and Void Distributions In Multi-pin geometry. NURETH-IV, 1989, vol. 1, pp. 610–616.
29. 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.
30. Bergeonneau P., Rameau B. Conditions for Locally Stable Boiling in a Pin Bundle. Science and Technology Fast Reactor Safety. London, BNES, 1986. pp. 445–456.
31. Zhukov A.V., Sorokin A.P., Khudasko V.V. Vliyanie teplogidravlicheskikh faktorov na bezopasnost' TVS reaktorov [The influence of thermohydraulic factors on the safety of fuel assemblies of reactors]. Obninsk, Obninsk Institute of Atomic Energy Publ., 1990. 82 p.
32. Sorokin A.P., Efanov A.D., Ivanov E.F., Martsinyuk D.E., Bogoslovskaya G.P., Rymkevich K.S., Malkov V.L. Raschetno-eksperimental'nye issledovaniya usloviy ustoychivogo teploobmena pri vozniknovenii kipeniya zhidkogo metalla v rezhime avariynogo raskholazhivaniya bystrogo reaktora [Numerical and experimental studies of the conditions of stable heat transfer in the event of boiling liquid metal in the accident regimes of a fast reactor]. Izvestiya vuzov. Yadernaya energetika – Proseedings of Universities. Nuclear Power Engineering, 1999, no. 2, pp. 59–70.
33. Sorokin A.P., Efanov A.D., Ivanov E.F., Martsinyuk D.E., Bogoslovskaya G.P., Rymkevich K.S., Malkov V.L. Teploobmen pri kipenii zhidkogo metalla v rezhime avariynogo raskholazhivaniya bystrogo reaktora [Heat transfer during the boiling of liquid metal in the emergency cooldown mode of a fast reactor]. Atomnaya energiya – Atomic Energy, 1999, vol. 87, no. 5, pp. 337–342.
34. Efanov A.D., Sorokin A.P., Ivanov E.F., Bogoslovskaya G.P., Kolesnik V.P., Martsinyuk S.S., Malkov V.L., Sorokin G.A., Rymkevich K.S. FROM. Issledovaniya teploobmena i ustoychivosti kipeniya zhidkometallicheskogo teplonositelya v konture estestvennoy tsirkulyatsii [Studies of heat transfer and boiling stability of a liquid metal coolant in the natural circulation loop]. Teploenergetika – Thermal Engineering, 2003, no. 3, pp. 20–26.
35. 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.
36. 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. Eleventh International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-11). Avignon, France, 2005.
37. 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 during boiling of a liquid metal in a channel system in the natural circulation regime]. Teploenergetika – Thermal Engineering, 2007, no. 3, pp. 43–51.
38. 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.
39. Sorokin A.P., Kuzina Yu.A., Ivanov E.F. Teploobmen pri kipenii zhidkometallicheskikh teplonositeley v TVS bystrykh reaktorov v avariynykh rezhimakh [Heat transfer during boiling of liquid metal coolants in fuel assemblies of fast reactors in emergency conditions. Voprosy Atomnoy Nauki i Tekhniki. Seriya: Yaderno-reaktornye konstanty – Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2018, no. 3, pp. 176–194.
40. 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.
41. Volkov A.V., Kuznetsov I.A. Usovershenstvovannaya model' kipeniya natriya dlya analiza avariy v bystrom reaktore [An improved model of sodium boiling for analysis of accidents in a fast reactor. Izvestiya vuzov. Yadernaya energetika – Proseedings of Universities. Nuclear Power Engineering, 2006, no. 2, pp. 101–111.
42. Kasahara F., Ninokata H., Sorokin A.P., Bogoslovskaya G.P. Analysis of liquid-metal boiling under the natural circulation condition. NTHAS2: Proc. Second Japan – Korea symposium on nuclear thermal hydraulics and safety. Fukuoka, Japan, 2000.
43. 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'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 during boiling of a liquid metal in a system of parallel fuel assemblies in the mode of natural convection. Izvestiya vuzov. Yadernaya energetika – Proseedings of Universities. Nuclear Power Engineering, 2005, no. 4, pp. 92–106.
44. Borishansky V.M., Andreevsky A.A., Zhokhov K.A., Bykov G.S., Svetlova L.S. Teplootdacha pri kipenii kaliya v trube v oblasti umerennogo parosoderzhaniya [Heat transfer when boiling potassium in a pipe in the region of moderate vapor content]. Atomnaya energiya – Atomic Energy, 1966, vol. 21, no. 1, pp. 58.
45. Aladyev R.T., Gorlov I.G., Dodonov L.D. et. al. Teploobmen pri kipenii kaliya v trubakh s ravnomernym teplopodvodom [Heat transfer during boiling of potassium in pipes with uniform heat supply. Izvestiya
AN SSSR. Energetika i transport – Proceedings of the USSR Academy of Sciences. Series: Energy and Transport, 1966, no. 2, pp. 136.
46. 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 the boiling of potassium in pipes]. Teplofizika vysokikh temperatur – High Temperature, 1968, vol. 6, no. 4, pp. 682–690.
47. Kirillov P.L. Bank dannykh po teploobmenu v zhidkikh metallakh, Chast' 2. Teploobmen pri kipenii zhidkikh metallov [Databank on heat transfer in liquid metals, Part 2. Heat transfer during boiling of liquid metals]. Preprint FEI-3276 – Preprint IPPE-3276. Obninsk, 2017. 40 p.
48. 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.
49. 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.
50. 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.
51. Wallis G. Odnomernye dvukhfaznye techeniya [One-dimensional biphasic flows]. Moscow, Mir Publ., 1972. 440 p.
52. Yagov V.V. Teploobmen v odnofaznykh sredakh i pri fazovykh prevrashcheniyakh: uchebnoe posobie dlya vuzov [Heat transfer in single-phase media and during phase transformations: a textbook for universities]. Moscow, Publishing House MPEI, 2014. 542 p.
53. Gogonin I.I. Zavisimost' teploobmena pri kipenii ot svoystv geometricheskikh parametrov teplootdayushchey stenki [The dependence of heat transfer during boiling on the properties of the geometric parameters of the heat-releasing wall]. Teplofizika vysokikh temperatur – High Temperature, 2006, vol. 44, no. 6, pp. 918–925.
54. Grigoriev V.A., Pavlov Yu.M., Ametistov E.V. Kipenie kriogennykh zhidkostey [Boiling cryogenic liquids]. Moscow, Energy Publ., 1977. 289 p.
55. Galin N.M., Kirillov P.L. Teplomassoobmen (v yadernoy energetike) [Heat and mass transfer (in nuclear energy)]. Moscow, Energoatomizdat Publ., 1987. 289 p.
56. Prisnyakov V.F. Kipenie [Boiling]. Kiev, Naukova Dumka Publ., 1988. 240 p.
57. Pershukov V.A., Arkhangelsky N.V., Kononov O.E., Sorokin A.P. Teplofizicheskaya stendovaya baza atomnoy energetiki Rossii i Kazakhstana [Thermophysical stands base of nuclear energy in Russia and Kazakhstan]. Sarov, FSUE RFNC-VNIIEF Publ., 2016. 160 p.
58. Sorokin A.P., Kuzina Yu.A., Ivanov E.F. Osobennosti teploobmena pri kipenii zhidkogo metalla v avariynykh rezhimakh v TVS bystrykh reaktorov [Features of heat transfer during boiling of liquid metal in emergency conditions in fuel assemblies of fast reactors]. Atomnaya energiya – Atomic Energy, 2019, vol. 126, no. 2, pp. 69–76.
59. Sorokin A.P., Ivanov E.F., Malkov V.L., Kolesnik V.P., Martsinyuk D.E., Rymkevich K.S., Korhov O.A. Eksperimental'nye issledovaniya teploobmena i ustoychivosti kipeniya zhidkometallicheskogo teplonositelya v konture estestvennoy tsirkulyatsii [Experimental studies of heat transfer and boiling stability of a liquid metal coolant in a natural circulation circuit]. Preprint FEI-2631 – Preprint IPPE-2631. Obninsk, 1997. 32 р.
60. 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. Proc. 11th International Heat Transfer Conference. Kyongju, Korea, 1998, vol. 2, pp. 357–361.
61. 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.
62. 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.
63. Khabensky V.B., Gerliga V.A. Nestabil'nost' potoka teplonositelya v elementakh oborudovaniya [Instability of the flow of coolant in the elements of equipment]. St. Petersburg, Science Publ., 1994.
64. 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.
65. 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.
66. 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. International Conference on Nuclear Engineering, ASME. New Orleans, Louisiana, 1996, vol. 1, part 1, pp. 373–383.