Authors & Affiliations
Grabezhnaya V.A., Mikheyev A.S., Kryukov A.E.
A.I. Leypunsky Institute for Physics and Power Engineering, Obninsk, Russia
Mikheyev A.S. – Senior Researcher.
Kryukov A.E. – Leading Engineer.
The BREST-OD-300 steam generator project being developed at NIKIET is pioneering both in terms of the heat carrier used (lead) and in design implementation (coils of helical heat transfer tubes). The advantages of the designs of steam generators made in the form of helical coiled tubes, in comparison with straight tube designs are obvious. Helical coiled tubes are used in heat exchange equipment not only to increase the heat transfer surface, to solve the problem of thermal expansion, but also to increase the coefficient of heat transfer to the fluid flowing inside the tubes. In 2011–2017 years the thermohydraulic tests of various models of lead-heated steam generator were carried out at the IPPE SPRUT facility (IPPE). The test program was aimed to study the heat transfer and the thermal-hydraulic stability of the steam generating tubes. Throughout the entire range of changes in operating parameters, no pulsating modes were detected with overturn of circulation in the water circuit. The design temperatures of superheated steam were obtained in nominal operation. The results provide extensive information on water heat transfer in different zones of the steam generating channel under various operating conditions (nominal and partial modes, starting modes). However, to verify the computer codes, experimental data on the heat transfer of lead coolant around the bundles of heat transfer tubes are necessary. Due to the small twist angle of the tubes in a full-scale steam generator, it can be said that heat transfer is close to heat transfer during transverse flow. A model with a transverse flow of lead coolant around steam-generating tubes was developed at the SSC RF – IPPE. The main goal of the research was to obtain data on the effect of oxygen concentration in lead on heat transfer in normal heat transfer modes and with lead freezing. Throughout the entire range of changes in the initial temperature values of lead and water, blocking of the annular space by frozen lead was not recorded.
steam generator, heavy liquid metal coolant, the bundle of heat transfer tubes, transverse flow, lead, water, experiment, heat transfer coefficient, basic oxygen regime, lead on the oxygen saturation line, lead freezing
1. Grabezhnaya V.A., Mikheyev A.S., Stein Yu.Yu., Kryukov A.E. Rezul'taty ispytaniy modeli parogeneratora BREST v usloviyakh chastichnykh i puskovykh rezhimov [Results of tests of the BREST steam generator model under conditions of partial and start-up modes]. Trudy nauchno-tekhnicheskoy konferentsii “Teplofizika reaktorov na bystrykh neytronakh (Teplofizika-2013)” [Proc. Sci. Tech. Conf. “Thermophysics of Fast Neutron Reactors (Thermophysics-2013)”]. Obninsk, 2013, vol. 1, pp. 287–293.
2. Grabezhnaya V.A., Kryukov A.E., Mikheyev A.S., Stein Yu.Yu. Nekotoryye rezul'taty is-sledovaniya modeli vitogo parogeneratora, obogrevayemogo svintsom [Some results of the study of a model of a twisted steam generator heated by lead]. Trudy konferentsii “Tyazhelye zhidkometallicheskie teplonositeli v yadernykh tekhnologiyakh” [Proc. Sci. Tech. Conf. “Heavy Liquid-Metal Coolants in Nuclear Technology (HLMC-2013)”]. Obninsk, 2014, vol. 1, pp. 139–152.
3. Kalyakin S.G., Grachev N.S., Grabezhnaya V.A. et al. Eksperimental'noye issledovaniye teploobmena v zhidkom metalle v obosnovaniye paro-generatora ustanovki RU BREST-OD-300 [Experimental study of heat transfer in liquid metal to justify the steam generator of the BREST-OD-300 RU installation]. Trudy 3 Rossiyskoy konferentsii po teploobmenu (RNKT-3) [Proc. 3th Russian Conf. on Heat Transfer (RNHTC-3)]. Moscow, 2002, vol. 2, pp. 159–162.
4. Kalyakin S.G., Grabezhnaya V.A. Eksperimental'noye issledovaniye teploobmena v zhidkom metalle pri poperechnom obtekanii puchka trub v obosnovaniye parogeneratora ustanovki RU BREST-OD-300 [Experimental study of heat transfer in a liquid metal with a transverse flow around a tube bundle to substantiate the steam generator of the BREST-OD-300 reactor plant]. Trudy 4 Rossiyskoy natsional'noy konferentsii po teploobmenu [Proc. 4th Russian Conf. on Heat Transfer (RNHTC-4)]. Moscow, 2006, vol. 2, pp. 128–131.
5. Shcherbakov S.I. Numerical simulation of nonsteady-state multiphase flow. The 2D TURBO-FLOW computer code used to perform express analysis of designs. Proc. 11 Int. Topical Meeting on Nuclear Reactor Thermal Hydraulics NURETH-11. Avignon, France, 2005, p. 238.
6. Parfenov A.S., Mikheyev A.S., Grabezhnaya V.A., Shcherbakov S.I. Eksperimental'noye issledovaniye teploobmena pri poperechnom obtekanii svintsom puchka parogeneriruyushchikh trub [Experimental study of heat transfer in a transverse flow of lead around a bundle of steam-generating tubes]. Trudy nauchno-tekhnicheskoy konferentsii “Teplofizika reaktorov na bystrykh neytronakh (Teplofizika-2013)” [Proc. Sci. Tech. Conf. “Thermophysics of Fast Neutron Reactors (Teplofizika-2013)”]. Obninsk, 2013, vol. 1, pp. 294–299.
7. Loginov N.I. Elektromagnitnyye preobrazovateli raskhoda zhidkikh metallov [Electromagnetic liquid metal flow transducers]. Moscow, Energoizdat Publ., 1981.
8. Kirillov P.L., Yur'yev Yu.S., Bobkov V.P. Spravochnik po teplogidravlicheskim raschetam (yadernyye reaktory, teploobmenniki, parogeneratory) [Handbook of thermohydraulic calculations (nuclear reactors, heat exchangers, steam generators)]. Moscow, Energoatomizdat Publ., 1990.
9. Petukhov B.S., Kirillov V.V. K voprosu o teploobmene pri turbulentnom techenii zhidkosti v trubakh [On the issue of heat transfer in turbulent fluid flow in pipes]. Teploenergetika – Thermal Engineering, 1958, no. 4, pp. 63–68.
10. Zvorykin A., Mahdi M., Popov R. et. al. Heat transfer to supercritical water (liquid-like state) flowing in a short vertical bare tube with upward flow. Proc. 26th International Conference on Nuclear Engineering ICONE26. London, England, 2018, pp. ICONE26-81608.
11. ASME International Steam Tables for Industrial Use. New York: ASME Press, 1998.
12. Borishanskiy V.M., Andreyevskiy A.A., Zhilkina V.B., Shneyderman L.L. Teplootdacha pri poperechnom obtekanii puchkov trub zhidkim metallom [Heat transfer at transverse flow of liquid metal around tube bundles]. Moscow, Gosatomizdat Publ, 1963.
13. Beznosov A.V., Molodtsov A.A., Novozhilova O.O., Savinov S.Yu. Eksperimental'nyye is-sledovaniya teploobmena ot svintsovogo teplonositelya k poverkhnostyam vertikal'noy i go-rizontal'noy truby [Experimental studies of heat transfer from a lead coolant to the surfaces of a vertical and horizontal pipe]. Trudy nauchno-tekhnicheskoy konferentsii “Teplofizika reaktorov na bystrykh neytronakh “Teplofizika-2007” [Proc. Sci. and Techn. Conf. “Thermal Physics of Fast Reactors (Thermophysics-2007)”]. Obninsk, 2008, pp. 286–294.
14. Beznosov A.V., Novozhilova O.O., Savinov S.Yu., Molodtsov A.A. Eksperimental'nyye is-sledovaniya kharakteristik teploobmena na “goryachey” i “kholodnoy” poverkhnostyakh odnovremenno pri vvedenii v kontur svintsovogo teplonositelya primesey i ochistki ot nikh [Experimental studies of the characteristics of heat transfer on “hot” and “cold” surfaces simultaneously with the introduction of impurities into the lead coolant circuit and cleaning from them]. Trudy nauchno-tekhnicheskoy konferentsii “Teplofizika reaktorov na bystrykh neytronakh (Teplofizika-2007)” [Proc. Sci. and Techn. Conf. “Thermal Physics of Fast Reactors (Thermophysics-2007)”]. Obninsk, 2008, pp. 276–285.
15. Beznosov A.V., Semenov A.V., Molodtsov A.A. et al. Eksperimental'nyye issledovaniya vliya-niya primesi kisloroda na teplootdachu ot staley 10Х9НСМФБ i 12Х18Н10Т k svintsu i evtektike Li(17) Pb(83) [Experimental studies of the effect of oxygen impurity on heat transfer from steels 10Х9НСМФБ and 12Х18Н10Т to lead and Li(17) Pb(83)]. Trudy 4 Rossiyskoy natsional'noy konferentsii po teploobmenu [Proc. 4th Russian Conf. on Heat Transfer (RNHTC-4)]. Moscow, 2006, vol. 2, pp. 62–65.
16. Yarmonov M.V. Issledovaniya teploobmena pri poperechnom obtekanii trub tyazhelymi zhid-kometallicheskimi teplonositelyami reaktorov na bystrykh neytronakh. Diss. kand. tekhn. nauk [Investigations of heat transfer in cross-flow around pipes with heavy liquid-metal coolants of fast reactors. Cand. techn. sci. diss.]. Nizhniy Novgorod, 2014. 195 p.
17. Grabezhnaya V.A., Mikheev A.S. Vliyanie soderzhaniya kisloroda na teploobmen pri poperechnom obtekanii parogeneriruyushchikh trub tyazhelym zhidkometallicheskim teplonositelem [Influence of oxygen content on heat transfer in the case of a heavy liquid-metal coolant flowing past steam-generating pipes]. Atomnaya energiya – Atomic Energy, 2019, vol. 127, no. 4, pp. 11–18.