EDN: WRZEPC
Authors & Affiliations
Sorokin A.P., Kuzina Yu.A., Denisova N.A.
A.I. Leypunsky Institute for Physics and Power Engineering, Obninsk, Russia
Sorokin A.P. – Chief Researcher of Nuclear Energetic Department, Dr. Sci. (Tech.). Contacts: 1, pl. Bondarenko, Obninsk, Kaluga region, Russia, 249033. Tel.: +7 (484) 399-84-47; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Kuzina Ju.A. – Director of Nuclear Energetic Department, Cand. Sci. (Tech.).
Denisova N.A. – Lead Engineer of Nuclear Energetic Department.
Abstract
The article presents the results of thermohydraulic studies of the fast reactor core with liquid metal coolants, as well as the problems and tasks of further research. The main attention is paid to the results of studies obtained in substantiation of the reactor core of the nuclear power plant with the BN-350 reactor, which was put into operation 50 years ago, in 1973. The features of the formation of velocity and temperature fields in the core of fast reactors with liquid metal coolants are outlined and commented, which are largely related to the features of the thermophysical properties of liquid metals, as well as the design, neutron physics of the core and the influence of interchannel mass and heat transfer. The results of experimental studies of hydrodynamics obtained on models of rod bundles in air and liquid metal using the electromagnetic measurement method are presented and analyzed, which became the basis for the development of computational methods for determining the hydrodynamic characteristics of rod bundles longitudinally flown by a turbulent coolant flow. The results of experimental studies of heat transfer and temperature fields in the central and peripheral regions of fuel assemblies are presented in a wide range of parameters of fast reactor fuel assemblies. The results of computational modeling of thermal hydraulics in fuel assemblies of the core for nominal and non-nominal regimes of operation of fuel assemblies are presented. The influence of interchannel exchange on the formation of the temperature field, the influence of shape change due to the effects of radiation swelling and creep of steels during the campaign, etc. are analyzed.
Keywords
fast reactors, fuel assembly, thermal hydraulics, experiment, calculation methods, velocity, hydraulic resistance, heat transfer, heating, temperature nonuniformity, energy release, interchannel mixing, hot spots, shape change, stochastic deviation of parameters
Article Text (PDF, in Russian)
References
- Kuzina Yu.A., Sorokin A.P., Delnov V.N., Denisova N.A., Sorokin G.A. Thermophysical Studies of Alkaline Liquid Metal Coolants. Izvestiya vuzov. Yadernaya Energetika, 2022, no. 2, pp. 49–61.
- Subbotin V.I., Ibragimov M.Kh., Ushakov P.A., Bobkov V.P., Zhukov A.V., Yuriev Yu.S. Gidrodinamika i teploobmen v atomnykh energeticheskikh ustanovkakh (osnovy rascheta) [Hydrodynamics and heat transfer in nuclear power plants (bases of calculation)]. Moscow, Atomizdat Publ., 1975. 408 p.
- Zhukov A.V., Kirillov P.L., Matyukhin N.M., Sorokin A.P., Tikhomirov B.B., Ushakov P.A., Yuryev Yu.S., Mantlik F. et al. Teplogidravlicheskiy raschet TVS bystrykh reaktorov s zhidkometallicheskim okhlazhdeniyem [Thermal-hydraulic calculation of fuel assemblies of fast reactors with liquid metal cooling]. Moscow, Energoatomizdat , 1985. 157 p.
- Kazachkovskii O.D., Zhukov A.V., Sorokin A.P. et al. Temperature fields in fast reactor fuel assemblies with shape changes. At Energy, 1988, vol.65, iss. 2, pp. 627–636. DOI: https://doi.org/10.1007/
- Zhukov A.V., Sorokin A.P., Kirillov P.L., Ushakov P.A., Kiryushin A.I., Kuzavkov N.G. et al. Metodicheskiye ukazaniya i rekomendatsii po teplogidravlicheskomu raschetu aktivnykh zon bystrykh reaktorov. Pod obshchey redaktsiyey Zhukova A.V., Sorokina A.P. [Guidelines and recommendations for thermal-hydraulic calculation of the active zones of fast reactors. Ed. A.V. Zhukov, A.P. Sorokin]. RTM 1604.008-88, 1988. SCAE, IPPE, Approved and put into effect according to the Civil Code of the AE 13.10.88, No. GZh-6627/19.
- Bogoslovkaya 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 Russia Approaches. IAEA-TECDOC-1060. Vienna: IAEA. 1999.
- Sorokin A.P., Efanov A.D., Yuriev Yu.S., Zhukov A.V., Ushakov P.A., Bogoslovskaya G.P. Methods and Codes for Modelling Thermohydraulics of Fast Reactor Core Subassemblies under Nominal and Non-nominal Operation Conditions. LMFR Core Thermohydraulics: Status and Prospects. IAEA-TECDOC-1057. Vienna: IAEA. June 2000.
- Subbotin V.I., Ushakov P.A., Zhukov A.V., Talanov V.D., Kudryavtseva L.K., Sviridenko E.Ya., Vasilyeva L.V. Eksperimental'noye issledovaniye na modelyakh poley temperatury teplovydelyayushchikh elementov aktivnoy zony i ekrana reaktora BN-350 [Experimental study using models of temperature fields of the fuel-generating elements of the core and screen of the BN-350 reactor]. State Committee for the Institute of Atomic Energy of the USSR. IPPE, 1965. 22 p.
- Gordeyev S.S., Sorokin A.P. Osobennosti formirovaniya temperaturnogo polya aktivnoy zony reaktora na bystrykh neytronakh v protsesse kampanii [Features of formation of temperature field of the fast neutron reactors core during the campaign]. Voprosy atomnoy nauki i tekhniki. Seriya: Yaderno-reaktornyye konstanty – Problems of atomic science and technology. Series: Nuclear and Reactor Constants, 2018, no. 3, pp. 213–239. Available at: https://vant.ippe.ru/year2018/3/thermal-physics-hydrodynamics/1551-20.html (accessed 30.10.2023).
- Zhukov A.V., Sorokin A.P., Matyukhin N.M. Mezhkanal'nyy obmen v TVS bystrykh reaktorov: teoreticheskiye osnovy i fizika protsessa [Interchannel exchange in fuel assemblies of fast reactors: theoretical foundations and physics of the process]. Moscow, Energoatomizdat Publ., 1989. 183 p.
- Sorokin A.P., Kuzina Yu.A., Denisova N.A. Hydrodynamics of turbulent flows in fuel assemblies of fast reactors (velocity field and turbulence microstructure). Voprosy atomnoy nauki i tekhniki. Seriya: Yaderno-reaktornyye konstanty – Problems of atomic science and technology. Series: Nuclear and Reactor Constants, 2021, no. 2, pp. 139–166. DOI: 55176/2414-1038-2021-2-139-166.
- Zhukov A.V., Sorokin A.P., Titov P.A. et al. Analysis of the fast reactors' fuel-rod bundle flow resistance. At Energy, 1986, vol. 60, iss. 5, pp. 369–374. DOI: https://doi.org/10.1007/BF01125764.
- Rehme K. Widerstandsbeiwerte Von Gitterabstandshaltern for Reactor – brennelementen. Atomkernenergie, 1970, Bd. 15, N 2, S. 127–133.
- Chiu C., Todreas N. Flow split measurements in a LMFBR radial blanket assembly. TANS, 1977, vol. 26, pp. 455–456.
- Ushakov P.A. Priblizhennoye teplovoye modelirovaniye tsilindricheskikh teplovydelyayushchikh elementov. V kn. Zhidkiye metally [Approximate thermal modeling of cylindrical heat-releasing elements. In book: Liquid Metals]. Moscow, Atomizdat Publ., 1967. Pp. 137–148.
- Zhukov A.V., Sviridenko E.Ya., Matyukhin N.M. Eksperimental'noye issledovaniye temperaturnykh poley i teplootdachi v treugol'nykh reshetkakh imitatorov tvelov s zhidkometallicheskim okhlazhdeniyem [Experimental study of temperature fields and heat transfer in triangular lattices of fuel rod simulators with liquid metal cooling]. Preprint FEI-800 – Preprint IPPE-800. Obninsk, IPPE Publ., 1978. 15 p.
- Zhukov A.V., Sorokin A.P., Matyukhin N.M. Mezhkanal'nyy obmen v TVS bystrykh reaktorov: teoreticheskiye osnovy i fizika protsessa [Interchannel exchange in fuel assemblies of fast reactors: theoretical foundations and physics of the process]. Moscow, Energoatomizdat Publ., 1991. 225 p.
- Bogatyrev I.L., Bogoslovskaya G.P., Zhukov A.V., Sorokin A.P., Titov P.A. Sistema konstant dlya pokanal'nogo teplogidravlicheskogo rascheta rezhimov raboty TVS reaktorov s yestestvennoy i smeshannoy konvektsiyey [System of subchannel thermal-hydraulic calculation of regimes for reactors fuel assemblies with natural and mixed convection]. Preprint FEI-2238 – Preprint IPPE-2238. Obninsk, IPPE Publ., 1992. 37 p.
- Kazachkovsky O.D., Sorokin A.P., Zhukov A.V., Ushakov P.A., Bogoslovskaya G.P., Kriventsev V.I., Titov P.A. Metod sosredotochennykh parametrov v zadache o temperaturnom pole v formoizmenennykh TVS bystrykh reaktorov s neadiabaticheskimi granichnymi usloviyami [The Lumped Parameter Method in the Problem of the Temperature Field in Shaped Fuel Assemblies of Fast Reactors with Nonadiabatic Boundary Conditions]. Preprint FEI-1972 – Preprint IPPE-1972. Obninsk, IPPE Publ., 1985. 23 p.
- Kazachkovsky O.D., Sorokin A.P., Zhukov A.V., Ushakov P.A., Kriventsev V.A., Titov P.A. Stokhasticheskiye neravnomernosti temperaturnykh poley v formoizmenennykh TVS bystrykh reaktorov [Stochastic non-uniformities of temperature fields in shaped fuel assemblies of fast reactors]. Preprint FEI-1678 – Preprint IPPE-1678. Obninsk, IPPE Publ., 1985. 24 p.
- Sorokin A.P., Bogoslovskaya G.P. Metody teplogidravlicheskikh raschetov teplovydelyayushchikh sborok aktivnoy zony bystrykh reaktorov [Methods of thermohydraulic calculations of fuel assemblies of the active zone of fast reactors]. Teploenergetika – Thermal Engineering, 1997, vol. 3, pp. 21–26.
- Markley R.A., Engel F.C. LMFBR Blanket Assembly Heat Transfer and Hydraulic Test Data Evaluation. of the Specialist's Meeting “Thermodynamics of FBR Fuel Subassemblies under nominal and non-nominal operating conditions”. IAEA, Karlsruhe, February 5–7 1978, IWGFR/29. Pp. 229–253.
- Kravchenko I.N., Bagdasarov Yu.E., Likhachev Yu.I. Raschet na prochnost' tvelov i shestigrannogo chekhla TVS s uchetom sovmestnogo deformirovaniya tvelov i chekhla v protsesse oblucheniya v aktivnoy zone bystrogo reaktora [Calculation of the strength of fuel rods and a hexagonal cover of fuel assemblies, taking into account joint deformation of fuel elements and a cover during irradiation in the active zone of a fast reactor]. Preprint FEI-1840 – Preprint IPPE-1840. Obninsk, IPPE Publ., 22 p.
- Gordeev S.S., Sorokin A.P., Tikhomirov B.B. et al. Method of Calculating the Temperature Regimes of Fuel Elements in Fuel Assemblies Taking Account of Inter-Channel Coolant Mixing and Random Deviations of the Parameters. At Energy, 2017, vol. 122, iss. 1, pp. 19–28. DOI: https://doi.org/10.1007/s10512-017-0230-3
- Bogoslovskaya G.P., Zhukov A.V., Sorokin A.P., Khudasko V.V. Problemy optimizatsii teplogidravlik aktivnykh zon reaktorov s zhidkometallicheskim okhlazhdeniyem. Uchebnoye posobiye dlya slushateley kursov povysheniya kvalifikatsii i spetsial'nogo fakul'teta [Problems of optimizing the thermal hydraulics of the reactor core with liquid metal cooling. Textbook for students of advanced training courses and a special faculty]. Obninsk, 1991. 90 p.
- Zhukov A.V., Sorokin A.P., Khudasko V.V. Problemy teplogidravlik 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 regimes of reactor fuel assemblies with liquid metal cooling. Textbook for students of advanced training courses and a special faculty]. Obninsk, 1990. 106 p.
UDC 621.039.526:621.039.54
Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2023, no. 4, 1:12
