Authors & Affiliations
Sorokin A.P.1, Sorokin G.A.2, Kuzina Yu.A.1, Denisova N.A.1
1 A.I. Leypunsky Institute for Physics and Power Engineering, Obninsk, Russia
2 Moscow Institute of Physics and Technology, Moscow, Russia
Sorokin A.P.1 – Chief Researcher, Dr. Sci. (Tech.). Contacts: 1, pl. Bondarenko, Obninsk, Kaluga region, Russia, 249033. Tel.: +7 (484) 399-70-00 (add. 84-47); e-mail:
Abstract
Modern requirements for justification of operability of elements of the fast reactors core require determination of not only the level of maximum temperature of the fuel rod cladding, but also significantly greater detail in the temperature distribution along their perimeter, as well as the temperature distribution of the fuel assembly jacket. The article presents the methods of modeling heat exchange processes developed at IPPE JSC, developed sensors and measurement equipment directly on models in channels and fuel rod assemblies of fast reactors with alkaline liquid metal coolants. The results of experimental studies on test facilities with liquid metal coolants of heat exchange and temperature fields for laminar and turbulent flow regimes for a wide range of geometric parameters and flow characteristics of fuel rod assemblies of fast reactors are presented and analyzed. The article presents the results of studies of the influence of various factors on heat exchange and temperature fields of fuel elements for nominal and non-nominal conditions, including the operating conditions of the reactor during a campaign: the influence of the features of the geometry of the peripheral region of fuel assemblies, deformation of the fuel element lattice and fuel assembly jackets with deviation of geometric parameters (tolerances for manufacturing and placement of fuel elements, displacement, deflection, radiation swelling), non-uniformity of neutron flux (energy release), heat exchange through the fuel assembly jacket to coolant leakage in the gaps between fuel elements, various types of spacing of fuel elements, including multidirectional windings on fuel elements, etc. The effect of equalization of temperature fields in the cross-section of the fuel assembly due to interchannel heat and mass transfer is demonstrated. The dependences for coolant temperature distributions in the cross-section of the fuel assembly, heat transfer and azimuthal non-uniformity of the fuel element temperature under various geometric conditions and operating parameters obtained as a result of generalization of experimental data are presented. The degree of influence of various factors on the temperature regime in fuel rod assemblies is demonstrated. The presented data can be used both to justify the temperature regimes of fast reactor core and to verify thermal hydraulic calculation codes that take into account the influence of random (stochastic) and regular deviations of parameters on the temperature regime.
Keywords
fast reactors, liquid metals, experiment, heat exchange, reactor core, fuel assemblies, energy release, geometric, regime, technological factors, distribution of parameters, campaign, deformation, radiation effects, temperature, heating of coolant
Article Text (PDF, in Russian)
- Bogoslovskaya G.P., Denisova N.A., Sorokin A.P., Trufanov A.A. Issledovaniya vliyaniya radiatsionnogo formoizmeneniya TVS na temperaturnyy rezhim i napryazhenno-deformirovannoye sostoyaniye obolochki tvelov [Research of the influence of radiation-induced deformation of fuel assemblies on the temperature regime and the stress-strain state of the fuel element cladding]. Teplofizika: sbornik statey k 65-letiyu sozdaniya Teplofizicheskogo otdela FEI. Pod red. Yu.A. Kuzinoy, A.P. Sorokina. Tekhnicheskiy redaktor N.A. Denisova [Thermophysics: collection of articles for the 65th anniversary of the creation of the Thermophysical Department of the IPPE. Ed. Yu.A. Kuzina, A.P. Sorokin. Technical editor N.A. Denisova]. Obninsk, IPPE, 2019, pp. 51–61.
- Zhukov A.V., Sorokin A.P., Kirillov P.L., Ushakov P.A., Kiryushin A.I., Kuzavkov N.G. Metodicheskie ukazaniya i rekomendatsii po teplogidravlicheskomu raschetu aktivnykh zon bystrykh reaktorov [Methodological guidelines and recommendations for thermohydraulic calculation of fast reactor cores]. RTM 1604.008-88. Obninsk, ONTI FEI Publ., 1988. 436 p.
- Bogoslovskaya G.P., Cevolani S., Ninokata H., Rinejski A.A., Sorokin A.P., Zhukov A.V. LMFR core and heat exchanger thermohydraulic design: former USSR and present Russian approaches. IAEA-TECDOC-1060. Vienna: IAEA, 1998. 303 p.
- The Fast Reactors Thermohydraulics for Cooling by Various Coolants. Proc. of 10-th International Meeting of the IAHR Working Group on Advanced Nuclear Reactor Thermal Hydraulics. Obninsk, July 17–19, 2001. Obninsk: IPPE, 2003. 284 p.
- Hydrodynamics and heat transfer in reactor components cooled by liquid coolant in single/two-phase (working material). Proc. of the 11th Meeting of the International Association for Hydraulic Research (IAHR). Obninsk, IPPE, July 5–9, 2004. IAEA-TWG-FR/125. Vienna: IAEA, 2005. 499 p.
- Kuzina Yu.A., Sorokin A.P. Teplofizika shchelochnykh zhidkikh metallov. Chast' 1: Teplogidravlika i bezopasnost' (retrospektivno-perspektivnyy vzglyad) [Thermal physics of alkali liquid metals. Part 1: thermal hydraulics and safety (retrospective and prospective view)]. Voprosy atomnoy nauki i tekhniki. Seriya: Yaderno-reaktornyye konstanty – Problems of Atomic Science and Technology Series: Nuclear and Reactor Constants, 2019, no. 3, pp. 210–232.
- Subbotin V.I., Ibragimov M.Kh., Ushakov P.A., Bobkov V.P., Zhukov A.V., Yuryev Yu.S. Gidrodinamika i teploobmen v atomnykh energeticheskikh ustanovkakh (osnovy rascheta) [Hydrodynamics and heat transfer in nuclear power plants (calculation principles)]. Moscow, Atomizdat Publ., 1975. 408 p.
- Ushakov P.A., Zhukov A.V., Yuryev Yu.S. et al. Issledovanie poley temperatury v pravil’nykh i deformirovannykh reshetkakh tvelov reaktorov [Study of temperature fields in regular and deformed lattices of reactor fuel elements]. Trudy SEV [Proc. CMEA]. Obninsk, ONTI FEI Publ., 1980.
- Zhukov A.V., Sorokin A.P., Matyukhin N.M. Heat removal in fast reactor cores. At Energy, 1985, vol. 58, issue 4, pp. 250–258. DOI: https://doi.org/10.1007/BF01207211.
- Hoffmann Н., Hoffmann F., Rehme К. Status of the LMFBR Thermo- and Fluid-Dynamic Activities at KFK. Thermodynamics of FBR Fuel Subassemblies under Nominal and Non-Nominal Operating Conditions. IAEA-IWGFR/29. Vienna: IAEA, 1979, pp. 82–106.
- Gnadt P.A., Carbajo J.J., Dearing J.P. et al. Sodium Boiling Experiments in the Thors Facility. Nuclear Engineering and Design, 1984, vol. 82, no. 1–3, pp. 241–280.
- Markley R.A. Status of Core Thermо-Hydraulic Development in the USA. Thermodynamics of FBR Fuel Subassemblies under Nominal and Non-Nominal Operating Conditions. IAEA-IWGFR/29. Vienna: IAEA, 1979, pp. 76–81.
- Chiu C., Todreas N., et al. Experimental Techniques for Liquid Metal Cooled Fast Breeder Reactor Fuel Assembly Thermal/Hydraulic Test. Nuclear Engineering and Design, 1980, vol. 62, no. 1–3, pp. 253–270.
- Engel F.G., Minushkin B., Atkins R.J. et al. Characterizations of Heat Transfer and Temperature Distributions in an Electrically Heated Model of an LMFBR Blanket Assembly. Nuclear Engineering and Design, 1980, vol. 62, no. 1–3, pp. 335–347.
- Levis A.E., Wantland J.L. A Study of the Reproducibility of Data from Steady-State Tests in Simulated Liquid-Metal Fast Breeder Reactor Fuel Assemblies. Nuclear Technology, 1984, vol. 67, no. 2, pp. 132–148.
- Mijaguchi K., Takahashi J. Thermal-Hydraulic Experiments with Simulated LMFBR Subassemblies under Nominal and Non-Nominal Operating Conditions. Thermodynamics of FBR Fuel Subassemblies under Nominal and Non-Nominal Operating Conditions. IAEA-IWGFR/29. Vienna: IAEA, 1979, pp. 58–75.
- Betts C., Mc Areavey C.G. A Review of Theoretical and Experimental Studies underlying the Thermal-Hydraulic Design of Fast Reactor Fuel Elements. Thermodynamics of FBR Fuel Subassemblies under Nominal and Non-Nominal Operating Conditions. IAEA-IWGFR/29. Vienna: IAEA, 1979, pp. 7–22.
- Khairallah A., Leteinturier D., Sksk J. Status of Thermohydraulic Studies of Wire-Wrapped Bundles. Thermodynamics of FBR Fuel Subassemblies under Nominal and Non-Nominal Operating Conditions. IAEA-IWGFR/29. Vienna: IAEA, 1979, pp. 23–28.
- Menant В., Basque G., Grand D. Theoretical Analysis and Experimental Evidence of Three Types of Thermohydraulic Incohorency in Undisturbed Cluster Geometry. Thermodynamics of FBR Fuel Subassemblies under Nominal and Non-Nominal Operating Conditions. IAEA-IWGFR/29. Vienna: IAEA, 1979, pp. 134–151.
- Leteinturier D., Cartier L. Theoretical and Experimental Investigations of the Thermohydraulics of Deformed Wire-Wrapped Bundles in Nominal Flow Conditions. Thermodynamics of FBR Fuel Subassemblies under Nominal and Non-Nominal Operating Conditions. IAEA-IWGFR/29. Vienna: IAEA, 1979, pp. 254–260.
- Weber G., Cornet G. Thermohydraulic Characteristics of SNR-Fuel Elements. Thermodynamics of FBR Fuel Subassemblies under Nominal and Non-Nominal Operating Conditions. IAEA-IWGFR/29. Vienna: IAEA, 1979, pp. 202–215.
- Falzetti, Meneghello S., Pezzilli M. Steady-State Thermohydraulic Studies in Seven-Pin Bundle Out-of-Pile Experiments: Nominal and Distorted Geometry Tests. Thermodynamics of FBR Fuel Subassemblies under Nominal and Non-Nominal Operating Conditions. IAEA-IWGFR/29. Vienna: IAEA, 1979, pp. 261–273.
- Mantlik F. Current state of sodium dynamics issues in fast reactors core. Hydrodynamics and heat transfer in core and steam generators of fast reactors with sodium coolant. Prague, ČSKAE Publ., 1984. Vol. 1, pp. 14–22.
- Schulz V. Experimental study of temperature fields in a fast reactor cassette with damaged beam geometry. Hydrodynamics and heat transfer in core and steam generators of fast reactors with sodium coolant. Prague, ČSKAE Publ., 1984. Vol. 1, pp. 159–173.
- Gryazev V.M., Aseev N.A., Markin S.A. et al. Calculation and experimental studies of thermal physics and hydrodynamics of the BOR-60 reactor core packages. Thermal physics and hydrodynamics of the core and steam generators for fast reactors. Prague, ČhSKAE Publ., 1978. Vol. 1, pp. 182–209.
- Minashin V.E., Subbotin V.I., Ushakov P.A., Sholokhov A.A. Priminenie mikrotermopar v issledovanii teplootdachi. Voprosy teploobmena [Application of microthermocouples in heat transfer studies. Heat Transfer Issues]. Moscow, Izd-vo AN SSSR Publ., 1959. Pp. 193–199.
- Minashin V.E., Ushakov P.A., Sholokhov A.A. Ob oshibke izmereniya temperatury za schet iskazheniya izoterm v rayone zadelki termopar. Konvektivnyy i luchistyy teploobmen [On the error in temperature measurement due to distortion of isotherms in the area of thermocouple sealing. Convective and radiant heat exchange]. Moscow, Izd-vo AN SSSR Publ, 1960.
- Kirillov P.L., Subbotin V.I., Suvorov M.Ya., Troyanov M.F. Teplootdacha k splavu natriya s kaliem i k rtuti [Heat transfer to an alloy of sodium with potassium and to mercury]. Atomnaya energiya – Atomic Energy, 1959, vol. 6, issue 4, pp. 382–390.
- Zhukov A.V., Kudryavtseva L.K., Sviridenko E.Ya., Subbotin V.I., Talanov V.D., Ushakov P.A. Eksperimental'noye issledovaniye na modelyakh poley temperatury teplovydelyayushchikh elementov [Experimental study on models of temperature fields of fuel elements]. Sbornik statey “Zhidkiye metally”. Pod red. P.L. Kirillova, V.I. Subbotina, P.A. Ushakova [Collection of articles “Liquid Metals” Ed. P.L. Kirillov, V.I. Subbotin, P.A. Ushakov]. Moscow, Atomizdat Publ., 1967. Pp. 170–194.
- Petukhov B.S. Teploobmen i soprotivlenie pri laminarnom techenii zhidkosti v trubah [Heat transfer and resistance during laminar flow of liquid in pipes]. Moscow, Energiya Publ., 1967.
- Labuntsov D.A. Nekotorye voprosy teorii teploovmena pri laminarnom techenii zhidkosti v trubah [Some issues of heat transfer theory during laminar flow of liquid in pipes]. Teploenergetika – Thermal engineering, 1958, no. 3, p. 87.
- Petukhov B.S., Genin L.G., Kovalev S.A., Soloviev S.L. Teploobmen v yadernyh energeticheskih ustanovkah [Heat exchange in nuclear power plants]. Moscow, Izd-vo MEI Publ., 2003.
- Ibragimov M.K., Zhukov A.V. A method for computing heat transfer coefficients for longitudinal flow of liquid metals through fuel elements bundles. At Energy, 1966, vol. 20, issue 5, p. 483. DOI: https://doi.org/10.1007/BF01164051.
- Kirillov P.L. Generalization of experimental data on heat transfer in molten metals. The Soviet Journal of Atomic Energy, 1963, vol. 13, issue 5, pp. 1103–1106. DOI: https://doi.org/10.1007/BF01479828.
- Ibragimov M.Kh., Subbotin V.I., Bobkov V.P., Sabelev G.I., Taranov G.S. Struktura turbulentnykh potokov v kanalakh [Structure of turbulent flows in channels]. Moscow, Atomizdat Publ., 1978. 296 p.
- Borishansky V.M., Kutateladze S.S., Novikov I.I., Fedynsky O.S. Zhidkometallicheskie teplonositeli. Izd. 3-e. [Liquid metal coolants. 3rd ed.]. Moscow, Atomizdat Publ., 1976.
- Subbotin V.I., Ibragimov M.K., Ivanovskii M.N. et al. Heat-transfer from the turbulent flow of liquid metals in tubes. The Soviet Journal of Atomic Energy, 1962, vol. 11, issue 2, pp. 769–775. DOI: https://doi.org/10.1007/BF01626445.
- Kirillov P.L., Sorokin A.P. Teploobmen zhidkikh metallov [Heat transfer of liquid metals]. Sbornik statey “Zhidkiye metally: ot pervogo teplofizicheskogo stenda k krupnomasshtabnoy atomnoy energetike”. Pod red. A.D. Efanova, F.A. Kozlova [Collection of articles “Liquid Metals: from first thermophizical test facility to large scale atomic energy”. Ed. A.D. Efanov, F.A. Kozlov]. Obninsk, FEI Publ., 2001. P. 56.
- Kirillov P.L. Teploobmen zhidkikh metallov v kruglykh trubakh (odnofaznyy i dvukhfaznyy potoki). Avtoref. dis. tekh. nauk [Heat transfer of liquid metals in round pipes (single-phase and two-phase flows). Diss. abstract. dr. tech. sci.]. Moscow, IVTAN USSR Publ., 1969.
- Dwyer O.E. Recent Development in Liquid Metal Heat Transfer. N.Y.: Brokhaven National Laboratory Upton, 1969. P. 2009.
- Petukhov B.S., Yushin A.Ya. O teploobmene pri techenii zhidkogo metalla v laminarnoy i perekhodnoy oblastyakh [On heat transfer during the flow of liquid metal in laminar and transition regions]. Doklady AN SSSR – USSR Academy of Sciences Reports, 1960, vol. 136, no. 6, p. 1321.
- Subbotin V.I., Ushakov P.A., Gabrianovich B.N., Talanov V.D., Sviridenko I.P. Teploobmen pri techenii zhidkikh metallov v kruglykh trubakh [Heat transfer during the flow of liquid metals in round pipes]. Inzhenerno-fizicheskiy zhurnal – Engineering Physics Journal, 1963, vol. 5, no. 4, pp. 16.
- Talanov V.D., Ushakov P.A. Teploovmen v kruglyh, kol’tsevyh i kvadratnyh kanalah. Sbornik statey “Zhidkiye metally”. Pod red. P.L. Kirillova, V.I. Subbotina, P.A. Ushakova [Heat transfer in round, annular and square channels. Collection of articles “Liquid Metals”. Ed. P.L. Kirillov, V.I. Subbotin, P.A. Ushakov]. Moscow, Atomizdat Publ., 1967. Pp. 9–15.
- Subbotin V.I., Ivanovsky M.N., Orlov Yu.I. Termichskoe kontaktnoe soprotivlenie pri ohlazhdenii kanalov zhidkimi metallami [Thermal contact resistance during cooling of channels with liquid metals]. Teplofizika vysokikh temperatur – High Tempetature, 1967, vol. 5, no. 6, pp. 1025–1031.
- Kirillov P.L. Uchet kontaktnogo termicheskogo soprotivleniya teploobmenu zhidkogo metalla v krugloy trube [Accounting for contact thermal resistance to heat transfer of liquid metal in a round pipe]. Preprint FEI-284 – Preprint IPPE-284. Obninsk, FEI Publ., 1971.
- Ampliyev N.A., Kirillov P.L., Subbotin V.I., Suvorov M.Ya. Teploobmen zhidkogo metalla v vertikal'nykh trubakh pri nizkikh znacheniyakh chisel Re. Sbornik statey “Zhidkiye metally”. Pod red. P.L. Kirillova, V.I. Subbotina, P.A. Ushakova [Heat transfer of liquid metal in vertical pipes at low values of Pe numbers. Collection of articles “Liquid Metals”. Ed. P.L. Kirillov, V.I. Subbotin, P.A. Ushakov]. Moscow, Atomizdat Publ., 1967. Pp. 15–32.
- Ushakov P.A., Zhukov A.V., Matyukhin N.M. Temperaturnoye pole sterzhnevykh tvelov, raspolozhennykh v pravil'nykh reshetkakh pri laminarnom techenii teplonositely [Temperature field of fuel rods located in regular lattices with laminar coolant flow]. Teplofizika vysokikh temperatur – High Tempetature, 1976, vol. 14, no. 3, pp. 538–545.
- Kokorev L.S., Korsun A.S., Petrovichev V.I. Raschet stabilizirovannogo teploobmena pri prodol'nom obtekanii puchkov sterzhney [Calculation of stabilized heat transfer in longitudinal flow around rod bundles]. Voprosy teplofiziki yadernykh reaktorov – Problems of Nuclear Reactor Thermal Physics, 1970, no. 2, pp. 58–71.
- Sparrow E.M., Loeffler A.L., Hubbard H.A. Heat transfer to longitudinal laminar flow between cylinders. Journal Heat Transfer Transactions ASME, series C, 1961, vol. 83, no. 4, p. 415.
- Ushakov P.A., Zhukov A.V., Matyukhin N.M. Teplootdacha k zhidkim metallam v pravil'nykh reshetkakh tvelov [Heat transfer to liquid metals in regular lattices of fuel elements]. Teplofizika vysokikh temperatur – High Tempetature, 1971, vol. 15, no. 5, p. 1027.
- Dwyer O.E. Analytical Study of Heat Transfer to Liquid Metals Flowing in Line Through Closely Packed Rod Bundles. Nuclear Science and Engineering, 1966, vol. 25, p. 343.
- Ushakov P.A., Zhukov A.V., Matyukhin N.M. Azimutal'nyye neravnomernosti temperatury tvelov, raspolozhennykh v pravil'nykh reshetkakh, pri turbulentnom techenii zhidkikh metallov [Azimuthal non-uniformities of temperature of fuel elements located in regular lattices during turbulent flow of liquid metals]. Teplofizika vysokikh temperatur – High Tempetature, 1977, vol. 15, no. 1, p. 76.
- Zhukov A.V., Sidelnikov V.N., Titov P.A. Raschet temperaturnykh poley na nachal'nom uchastke reshetok tvelov (laminarnoye techeniye) [Calculation of temperature fields at the initial section of fuel element grids (laminar flow)]. Preprint FEI-491 – Preprint IPPE-491. Obninsk, FEI Publ., 1974. 20 p.
- Sidelnikov V.N., Zhukov A.V. Raschet temperaturnykh poley na nachal'nom uchastke reshetok tvelov i analiz vliyaniya peremennogo energovydeleniya (ploskoye techeniye teplonositelya) [Calculation of temperature fields at the initial section of fuel element grids and analysis of the influence of variable energy release (flat coolant flow)]. Preprint FEI-414 – Preprint IPPE-414. Obninsk, FEI Publ., 1973. 57 p.
- Zhukov A.V., Kirillova G.P. Raschet temperaturnykh poley na nachal'nom uchastke reshetok tvelov, obtekayemykh turbulentnym potokom zhidkometallicheskogo teplonositelya [Calculation of temperature fields at the initial section of fuel element grids, streamlined by a turbulent flow of liquid metal coolant]. Preprint FEI-715 – Preprint IPPE-715. Obninsk, FEI Publ., 1976. 22 p.
- Zhukov A.V., Matyukhin N.M., Kotovsky N.A., Sviridenko E.Ya. Eksperimental'noye issledovaniye temperaturnykh poley na nachal'nom uchastke puchkov sterzhney, obtekayemykh turbulentnym potokom zhidkometallicheskogo teplonositelya [Experimental study of temperature fields at the initial section of rod bundles, streamlined by a turbulent flow of liquid metal coolant]. Preprint FEI-781 – Preprint
IPPE-781. Obninsk, FEI Publ., 1977. 15 p. - Zhukov A.V., Kirillov P.L., Matyukhin N.M., Sorokin A.P., Tikhomirov B.B., Ushakov P.A., Yuryev Yu.S., Mantlik F., Geina J., Schmid J., Schultz V., Krett V. Teplogidravlicheskiy raschet TVS bystrykh reaktorov s zhidkometallicheskim okhlazhdeniyem [Thermohydraulic calculation of fuel assemblies of fast reactors with liquid metal cooling]. Fizika yadernykh reaktorov [Physics of Nuclear Reactors]. Moscow, Energoatomizdat Publ., 1985. Issue 129, 158 p.
- Zhukov A.V., Matyukhin N.M., Kotovsky N.A. et al. Eksperimental'noye i raschetnoye issledovaniye teploobmena v reshetkakh tvelov pri nestabilizirovannykh usloviyakh. Teploobmen i gidrodinamika odnofaznogo potoka v puchkakh sterzhney [Experimental and computational study of heat transfer in fuel element lattices under non-stabilized conditions. Heat transfer and hydrodynamics of single-phase flow in rod bundles]. Leningrad, Nauka, 1979. Pp. 108–112.
- Ushakov P.L., Sorokin A.P. Analiz primeneniya obobshchennogo integrala Dyuamelya dlya rascheta temperaturnogo polya tvelov reaktorov [Analysis of the application of the generalized Duhamel integral for calculating the temperature field of reactor fuel elements]. Teplofizika vysokikh temperatur – High Tempetature, 1978, vol. 16, no. 4, pp. 787–788.
- Dobrovol'skii V.F., Zhukov A.V., Sviridenko E.Ya., Subbotin V.I., Ushakov P.A Investigation of temperature fields in fast reactor fuel elements with variable power distribution over height of core. At Energy, 1970, vol. 28, issue 6, p. 621. DOI: https://doi.org/10.1007/BF01223630.
- Gubarev V.A., Trofimov A.S. Determination of wall-fluid temperature head in reactor thermal calculations. At Energy, 1974, vol. 37, issue 3, pp. 66–969. DOI: https://doi.org/10.1007/BF01120798.
- Katalog stendov, reaktorov nulevoy moshchnosti i drugikh eksperimental'nykh ustanovok [Catalog of test facilities, zero-power reactors and other experimental installations]. Izd. SEV Publ., KNTS 1-2, 1978. Pp. 20–22.
- Zhukov A.V., Sorokin A.P., Sviridenko E.Ya., Khudasko V.V. Eksperimental'noye i raschetnoye modelirovaniye teplogidravliki teploobmennykh apparatov YAEU. Model'nyye sborki, datchiki, metodiki. Zhidkometallicheskiy stend: uchebnoye posobiye dlya slushateley kursov povysheniya kvalifikatsii i spetsial'nogo fakul'teta [Experimental and computational modeling of thermal hydraulics of heat exchangers of nuclear power plants. Model assemblies, sensors, methods. Liquid metal test facility. Textbook for students of advanced training courses and special faculty]. Obninsk, IATE Publ., 1992. Pp. 59–76.
- Teplofizicheskaya stendovaya baza atomnoy energetiki Rossii i Kazakhstana. Pod red. Pershukova V.A., Arkhangel'skogo A.V., Kononova O.Ye., Sorokina A.P. [Thermophysical test bench base of nuclear power engineering of Russia and Kazakhstan. Ed. by V.A. Pershukov, A.V. Arkhangelsky, O.E. Kononov, A.P. Sorokin]. Sarov, FGUP “RFYATS – VNIIEF” Publ., 2016. 160 p.
- Subbotin V.I., Zhukov A.V., Pashek M., Sviridenko E.Ya., Ushakov P.A., Shultz V. Eksperimental'noye issledovaniye na modelyakh temperaturnykh rezhimov raboty tvel reaktora BOR-60 [Experimental study on models of temperature modes of operation of fuel elements of the BOR-60 reactor]. Preprint FEI-137 – Preprint IPPE-137. Obninsk, FEI Publ., 1969. 59 p.
- Zhukov A.V., Matyukhin N.M., Sviridenko E.Ya. Temperaturnyye polya i teplootdacha v periferiynykh zonakh shestigrannykh kasset tvelov bystrykh reaktorov [Temperature fields and heat transfer in the peripheral zones of hexagonal fuel rod bundles of fast reactors]. Voprosy atomnoy nauki i tekhniki. Seriya: Reaktorostroyeniye – Problems of Atomic Science and Technology. Series: Reactor Engineering, 1977, issue 4 (18), pp. 5–8.
- Zhukov A.V., Sorokin A.P., Ushakov P.A., Yuryev Yu.S. Vliyaniye mezhkanal'nogo obmena na vyravnivaniye poley skorosti i temperatury v kassetakh tvelov [Influence of interchannel exchange on the alignment of velocity and temperature fields in fuel rod bundles]. Preprint FEI-1062 – Preprint IPPE-1062. Obninsk, FEI Publ., 1980. 15 p.
- Kuzina Yu.A., Sorokin A.P., Denisova N.A. Eksperimental'noye modelirovaniye teploobmena v teplovydelyayushchikh sborkakh bystrykh reaktorov v avariynykh rezhimakh v usloviyakh yestestvennoy konvektsii [Experimental modeling of heat transfer in fuel assemblies of fast reactors in emergency modes under natural convection conditions]. Voprosy atomnoy nauki i tekhniki. Seriya: Yaderno-reaktornyye konstanty – Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2021, issue 4, pp. 106–120,
- Kutateladze S.S. Osnovy teorii teploobmena [Fundamentals of the Heat Transfer Theory]. Novosibirsk, Nauka, 1970.
- Subbotin V.I., Ushakov P.A., Zhukov A.V., Talanov V.A. The temperature distribution in liquid metal cooled fuel elements. At Energy, 1967, vol. 22, issue 5, pp. 468–474. DOI: https://doi.org/10.1007/BF01175209.
- Subbotin V.I., Zhukov A.V., Pashek M. et al. Experimental Study on Model of the Operating Temperature Regimes of the Fuel Elements of a BOR-60 Reactor. Heat Transfer, Soviet Research, 1971, vol. 3, no. 5, pp. 15–26.
- Zhukov A.V., Matyukhin N.M., Nomofilov E.V., Sorokin A.P., Yuryev Yu.S. Temperaturnyye polya v nestandartnykh i deformirovannykh reshetkakh tvelov bystrykh reaktorov [Temperature fields in non-standard and deformed lattices of fuel elements of fast reactors]. Teplofizika i gidrodinamika aktivnoy zony i parogeneratorov dlya bystrykh reaktorov [Thermal physics and hydrodynamics of the core and steam generators for fast reactors]. Prague, ČhSKAE Publ., 1978. Pp. 132–145.
- Sorokin A.P., Ushakov P.A., Yuryev Yu.S. et al. Vliyaniye mezhkanal'nogo obmena na vyravnivaniye poley skorosti i temperatury v kassetakh tvelov. Teplofizicheskiye i gidrodinamicheskiye issledovaniya v reaktorostroyenii [Effect of interchannel exchange on the alignment of velocity and temperature fields in fuel element cassettes. Thermophysical and hydrodynamic studies in reactor construction]. Voprosy atomnoy nauki i tekhniki. Seriya: Fizika i tekhnika yadernykh reaktorov – Problems of Atomic Science and Technology. Series: Physics and Technology Nuclear Reactor, 1984, vol. 4(41), pp. 63–69.
- Bogatirjev I.L., Zhukov N.M., Matyukhin N.M., Sorokin A.P., Ushakov P.A. Special Feature of Temperature Fuel Formation in the System of Interacting Fuel Subassemblies in Fast Reactor Core. LMFR Core Thermohydraulics Status and Prospects. IAEA-TECDOC-1057. Vienna: IAEA, 2000, p. 227–234.
- Proshkin A.A., Likhachev Yu.I., Tuzov A.N., Zabud'ko L.M., Bondarenko V.V., Karaulov V.N. An analysis of the experimental data concerning changes in the form of the fuel-breeding system of fast reactors. At Energy, 1981, vol. 50, issue 1, pp. 14–19. DOI: https://doi.org/10.1007/BF01141246.
- Kallnowski J.E., Banmgartner A.J. Reactor Assembly Bowing Predictions for Various Alloy Classes. Transactions of the American Nuclear Society, 1981, vol. 38, no. 1, p. 301.
- Parshin A.M. Struktura i radiatsionnoye raspukhaniye staley i splavov [Structure and radiation swelling of steels and alloys]. Moscow, Energoatomizdat Publ., 1983.
- Buksha Yu.K. Mezhdunarodnoye soveshchaniye po opytu i prognozirovaniyu povedeniya aktivnoy zony bystrykh reaktorov s uchetom formoizmeneniya TVS [International conference on experience and forecasting of the behavior of the core of fast reactors taking into account the change in the shape of fuel assemblies]. Atomic Energy, 1985, vol. 59, issue 6, pp. 453–455.
- Zhukov A.V., Sorokin A.P., Khudasko V.V. Problemy teplogidravliki nenominal'nykh rezhimov raboty TVS reaktorov s zhidkometallicheskim okhlazhdeniyem: uchebnoye posobiye dlya slushateley kursov povysheniya kvalifikatsii i spetsial'nogo fakul'teta [Problems of thermal hydraulics of non-nominal operating modes of fuel assemblies of reactors with liquid metal cooling. Textbook for students of advanced training courses and special faculty]. Obninsk, IATE Publ, 1990. 107 p.
- Kravchenko I.N., Bagdasarov Yu.E., Likhachev Yu.I. Raschet na prochnost' tvelov i shestigrannogo chekhla TVS s uchetom sovmestnogo deformirovaniya puchka tvelov i chekhla TVS v protsesse oblucheniya v aktivnoy zone bystrogo reaktora [Calculation of the strength of fuel rods and a hexagonal fuel assembly cover taking into account the combined deformation of the fuel rod bundle and the fuel assembly cover during irradiation in the core of a fast reactor]. Preprint FEI-1840 – Preprint IPPE-1840. Obninsk, FEI Publ., 1987.
- Matyukhin N.M. Nekotoryye voprosy vliyaniya smeshcheniya tvelov pravil'nykh reshetok na temperaturnyye polya i teploobmen (obzor literaturnykh dannykh) [Some issues of the influence of displacement of fuel elements in regular lattices on temperature fields and heat transfer (review of literary data)]. Preprint FEI-396 – Preprint IPPE-396. Obninsk, FEI Publ., 1973. 69 p.
- Zhukov A.V., Sorokin A.P., Ushakov P.A., Matyukhin N.M., Tikhomirov B.B., Titov P.A., Mantlik F., Schulz V. Teplofizicheskoye obosnovaniye temperaturnykh rezhimov TVS bystrykh reaktorov s uchetom faktorov peregreva (temperaturnyye polya, faktory peregreva) [Thermophysical substantiation of temperature regimes of fuel assemblies of fast reactors taking into account overheating factors (temperature fields, overheating factors)]. Preprint FEI-1778 – Preprint IPPE-1778. Obninsk, FEI Publ, 1986. 44 p.
- Kazachkovsky O.D., Zhukov A.V., Sorokin A.P., Matyukhin N.M. Temperature fields in fast reactor fuel assemblies with shape changes. At Energy, 1988, vol. 65, issue 2, pp. 627–636. DOI: https://doi.org/10.1007/BF01270803.
- LMFR Core and Heat Exchanger Thermohydraulic Design: Former USSR and Present Russia Approaches. IAEA-TECDOC-1060. Vienna: IAEA, 1999.
- Thermohydraulic investigations of increasing the burnup of nuclear fuel in fast-neutron reactors. Therm. Eng., 2007, vol. 54, issue 3, pp. 180–188. DOI: https://doi.org/10.1134/S0040601507030020.
- Zhukov A.V., Sorokin A.P., Khudasko V.V. Vliyaniye teplogidravlicheskikh faktorov na bezopasnost' TVS reaktorov: uchebnoye posobiye dlya slushateley KPK SP rukovodyashchikh rabotnikov Minatomenergo SSSR i studentov spets. 10.10. [Influence of thermal-hydraulic factors on the safety of reactor fuel assemblies. Textbook for students of the CIQ SP of executive employees of the USSR Ministry of Atomic Energy and students of specialties 10.10]. Obninsk, IATE Publ., 1990. 82 p.
- Kuzina Yu.A., Sorokin A.P., Zhukov A.V. Numerical simulation of the thermohydraulics of reactor fuel assemblies with blockages. At Energy, 1999, vol. 87, issue 5, pp. 808–822. DOI: https://doi.org/10.1007/
BF02673278. - Miyaguchi K., Takahaschi J. Thermal hydraulic Experiments and Simulated LMFBR Subassemblies under Nominal and Non-nominal Operating Conditions. Thermodynamics of FBR Fuel Subassemblies under Nominal and Non-Nominal Operating Conditions. IAEA-IWGFR/29. Vienna: IAEA, 1979, pp. 58–75.
- Nukamura H., Miyaguchi K., Takahashi J. Hydraulic Simulation of Local Blockages in LMFBR Fuel Subassembly. Nuclear Engineering and Design, 1980, vol. 60, no. 1–3, pp. 323–333.
- Spencer B.W. et al. Hydraulic Influences of Top-Generated Blockages in an LMFBR Subassembly. Transactions of the American Nuclear Society, 1980, vol. 34, pp. 521–522.
- Sha W.T. Effect of Partial Flow Blockages in an LMFBR Subassembly. Transactions of American Nuclear Society, 1972, vol. 15, no. 1, pp. 353–354.
- Arai M., Hirata N. Analysis of the Central Blockage Wake in an LMFBR Subassembly. Nuclear Engineering and Design, 1978, vol. 45, no. 1, pp. 127–132.
- Hanus N. et al. Maximum Sodium Temperature Correlation for Six-Channel FBR Subassemblu Blockage. Transactions of American Nuclear Society, 1978, vol. 30, pp. 417–418.
- Dearing J.F. Calculated vs Experimental Temperature Distribution behind Six-Channel Blockage. Transactions of the American Nuclear Society, 1977, vol. 27, pp. 566–567.
- Smidt D., Schleisiek K. Fast Breeder Safety against Propagation of Local Failures. Nuclear Engineering and Design, 1977, vol. 40, no. 3, pp. 393–402.
- Ushakov P.A., Yuryev Yu.S., Kolmakov A.P. Polya skorosti, davleniya i temperatury v kassete tvelov bystrykh reaktorov pri blokirovke prokhodnogo secheniya. Sbornik “Teplomassoobmen – V”. Pod red. A.G. Blokh [Fields of velocity, pressure and temperature in a fuel rod bundle of fast reactors with blocking of the flow section. Collection “Heat and Mass Transfer – V”. Ed. A.G. Blokh]. Minsk, ITMO AN SSSR Publ., 1980. Vol. 8, pp. 173–180.
- Zhukov A.V., Matyukhin N.M., Rymkevich K.S. Vliyaniye blokirovki prokhodnogo secheniya sborki kassety tvelov bystrogo reaktora na raspredeleniye skorosti teplonositelya [Effect of blocking the flow section of a fast reactor fuel rod assembly on the distribution of coolant velocity]. Preprint FEI-1479 – Preprint IPPE-1479. Obninsk, FEI Publ., 1983. 16 p.
- Kazachkovsky O.D., Zhukov A.V., Matyukhin N.M. et al. Intensifikatsiya teplomassoobmena v sborkakh tvelov bystrykh reaktorov s protivonapravlennymi provolochnymi navivkami pri neravnomernom po secheniyu sborki vydelenii [Intensification of heat and mass transfer in fast reactor fuel assemblies with counter-directional wire windings with non-uniform emission across the assembly cross-section]. Preprint FEI-1396 – Preprint IPPE-1396. Obninsk, FEI Publ., 1983.
- Zhukov A.V., Kuzina Yu.A., Sorokin A.P., Leonov V.N., Smirnov V.P., Sila-Novitsky A.G. Eksperimental'nyye issledovaniya teploperedachi v aktivnoy zone reaktora BREST-OD-300 na modelyakh so svintsovym okhlazhdeniyem [Experimental studies of heat transfer in the core of the BREST-OD-300 reactor on models with lead cooling]. Teploenergetika – Thermal Engineering, 2002, no. 3, pp. 2–10.
- Zhukov A.V., Kuzina Yu.A., Privezentsev V.V., Sorokin A.P., Glushakov D.A. Sravneniye temperaturnykh poley i teplootdachi v razdvinutykh reshetkakh (s/d = 1.33) i gladkikh tvelov s razlichnym distantsionirovaniyem (teplonositel' – zhidkiy metall) [Comparison of temperature fields and heat transfer in spread lattices (s/d = 1.33) and smooth fuel elements with different spacing (coolant – liquid metal)]. Sb. tezisov dokladov Nauchno-tekhnicheskoy konferentsii “Teplofizika reaktorov na bystrykh neytronakh (Teplofizika – 2014)” [Proc. of the Scientific and Technical Conference “Thermal physics of fast neutron reactors (Thermal physics – 2014)”]. Obninsk, IPPE, October 14–16, 2014, pp. 78–79.
- Zhukov A.V., Kuzina Yu.A., Sorokin A.P., Privezentsev V.V. Temperaturnyye polya i teplootdacha v razdvinutykh reshetkakh tvelov, okhlazhdayemykh tyazhelym zhidkometallicheskim teplonositelem [Temperature fields and heat transfer in separated grids of fuel elements cooled by heavy liquid metal coolant]. Izvestiya vuzov. Yadernaya Energetika, 2015, no. 4, pp. 90–100.
- Zhukov A.V., Sorokin A.P., Efanov A.D., Kuzina Yu.A. Temperaturnyye rezhimy tvelov korabel'nykh yadernykh ustanovok s zhidkometallicheskim okhlazhdeniyem [Temperature modes of fuel elements of ship nuclear installations with liquid metal cooling]. Izvestiya vuzov. Yadernaya Energetika, 2007, no. 1, pp. 56–68.
- Zhukov A.V., Matyukhin N.M., Sorokin A.P. Heat removal in fast reactor cores. At Energy, 1985, vol. 58, issue 4, pp. 250–258. DOI: https://doi.org/10.1007/BF01207211.
- Zhukov A.V., Sorokin A.P., Ushakov P.A., Matyukhin N.M., Titov P.A., Bogoslovskaya G.P., Tikhomirov B.B. An analysis of hot spots in fast reactor fuel assembly cores. At Energy, 1983, vol. 62, issue 3,pp. 183–189. DOI: https://doi.org/10.1007/BF01123483.
UDC 536.24:621.039.524.4:621.039.584
Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2026, no. 1, 1:15