EDN: SPQJZJ
Authors & Affiliations
Buriachenko N.K.1, Vakarin A.V.1, Gritsai A.S.1, 2, Popov A.O.1, Mitskevich A.V.1
1 Alexandrov Research Institute of Technology, Sosnovy Bor, Russia
2 Institute of Nuclear Power Engineering, Peter the Great St. Petersburg Polytechnic University, Sosnovy Bor, Russia
Buriachenko N.K.1 – Engineer.
Vakarin A.V.1 – Head of Group. Contacts: 72, Koporskoye shosse, Sosnovy Bor, Leningrad Region, Russia, 188540. Tel.: +7 (81369) 60-468; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Popov A.O.1 – Head of Group.
Mitskevich A.V.1 – Category 2nd Engineer.
Gritsai A.S.1, 2 – Deputy Director General for R&D, Cand. Sci. (Tech.).
Abstract
Interest is growing to the design of small modular reactors (SMR) as candidates in resolving the problem of shortage of electric and thermal power in distant regions. The primary cooling circuit of SMR can use water or heavy liquid metal as the coolant to remove heat from the reactor core. With all advantages of liquid metal cooling, there is a problem of experimentally demonstrating the performance capability of centrifugal or magnetohydrodynamic pumps. Therefore, transitioning to all-mode natural circulation of the coolant is addressed in a number of designs. In some design cases, the possibility is considered of using a gas lift to boost the natural circulation of liquid metal coolant and uprate the reactor power, with normal operating limits remaining unchanged and no pumps being used. This concept should be verified using validated computer codes.
The paper presents results of the KORSAR/LMC computer code validation for simulation of gas-lift enhanced natural circulation in heavy liquid metal cooled facilities. The validation was carried out by comparing calculation results with results of gas-lift experiments conducted in the NACIE and CIRCE test facilities. Using uncertainty and sensitivity analysis, the KORSAR/LMC closure relations with the most effect on results of gas-lift enhanced flow calculation are determined. The features of constitutive models on which the closure relations are based are described.
Keywords
computer code, KORSAR/LMC, heavy liquid metal coolant, CIRCE test facility, NACIE test facility, validation, uncertainty and sensitivity analysis, gas lift, calculation, closure relation
Article Text (PDF, in Russian)
References
- Lemehov V.V., Moisseyev A.V., Sarkulov M.K. i dr. Sovremennoye sostoyanie i perspektivy razvitiya reaktorov na bystryh neitronah so svintsovym teplonositelem [Modern status and future development of lead-cooled fast reactors]. Materialy 5-i mezhdunar. nauch.-tehn. konf. “Innovatsionnye proekty i tehnologii yadernoi energetiki (V MNTKNIKIET-2018) [Proc. of the 5th Int. Sci. and Techn. Conf. “Innovative Projects and Technologies in Nuclear Power (V ISTC NIKIET-2018)”]. Moscow, NIKIET, 2–5 October, 2018.
- Fedorovich E.D., Kurdiukov I.I. Analiticheskiy obzor opyta ekspluatatsii i sovremennyh razrabotok yadernyh energeticheskih ustanovok srednei i maloi moshchnosti s zhidkometallicheskim teplonositelem. Chast 2 (Sovremennye razrabotki) [Analytical review of operating experience and modern developments of medium and small power liquid metal cooled nuclear reactors. Part 2 (Modern developments)]. Tehnologii obespecheniya zhiznennogo tsikla yadernyh energeticheskih ustanovok – Nuclear Propulsion Reactor Plants. Life Cycle Management Technologies, 2020, no. 3(21), pp. 9–31.
- Roelofs F. Thermal Hydraulics Aspects of Liquid Metal Cooled Nuclear Reactors. Woodhead Publishing, 2019. 438 p. DOI: 10.1016/C2016-0-01216-0.
- Tarasov N.V., Lyakishev S.L., Sharyi N.V., Bezrukov Yu.A. Issledovanie zavisimosti razmerov osnovnogo oborudovaniya reaktornoi ustanovki s estestvennoi tsirkuliatsiei pervogo kontura ot tipa teplonositelya [Study of dependence of main equipment dimensions of reactor plant with natural circulation of primary circuit on type of coolant]. Voprosy atomnoy nauki i tekhniki. Seriya: Fizika yadernykh reaktorov – Problems of Atomic Science and Technology. Series: Nuclear Reactor Physics, 2022, issue 3, pp. 88–98.
- Yong-Hoon Shin, Sungyeol Choi, Jaehyun Cho, Sangrok Park, Il Soon Hwang. Design status of small modular reactor cooled by Lead-Bismuth eutectic natural circulation: URANUS. Proc. of ICONE, 23th International Conference on Nuclear Engineering.Chiba, Japan, May 17–21, 2015. DOI: 10.1299/jsmeicone.2015.23._ICONE23-2_51.
- Alekseev P.N., Mikityuk K.O., Vasiliev A.V., Fomichenko P.A., Shchepetina T.D., Subbotin S.A. Optimization of Conceptual Solutions for the RBETs-M Lead–Bismuth Fast Reactor. Atomic Energy, 2004, vol. 97, issue 2, pp. 551–558. DOI: https://doi.org/10.1023/B:ATEN.0000047681.87033.2e.
- Volkova S.N., Benediktov D.V., Vakarin A.V., Danilov I.G., Mitskevich A.V., Popov A.O., Yarushina A.V. Razrabotka, verifikatsiya i prakticheskoye ispolzovaniye raschetnogo koda KORSAR/ZHMT [Development, verification and application of the KORSAR/LMR computer code]. Tehnologii obespecheniya zhiznennogo tsikla yadernyh energeticheskih ustanovok– Nuclear Propulsion Reactor Plants. Life Cycle Management Technologies, 2021, no. 2(24), pp. 23–34.
- Vakarin A.V., Granovsky V.S., Gritsai A.S., Rumyantsev S.N. Modelirovanie prostranstvennoi gidrodinamiki v aktivnoi zone reaktornoi ustanovki stenda KM-1 [Simulation of 3D fluid dynamics in the reactor core of the KM-1 test facility]. Tehnologii obespecheniya zhiznennogo tsikla yadernyh energeticheskih ustanovok – Nuclear Propulsion Reactor Plants. Life Cycle Management Technologies, 2022, no. 2(28), pp. 26–37.
- Benamati G., Foletti С., Forgione N., Oriolo F., Scaddozzo G., Tarantino M. Experimental study on gas-injection enhanced circulation performed with the CIRCE facility. Nuclear Engineering and Design, 2007, vol. 237, no. 7, pp. 768–777.
- Turroni P., Cinotti L., Corsini G., Mansani L. The CIRCE Facility. AccApp’01&ADTTA’01, Nuclear Application in the new Millennium. Reno, 2001.
- Coccoluto G., Gaggini P., Labanti V., Tarantino M., Ambrosini W., Forgione N., Napoli A., Oriolo F. Heavy Liquid Metal Natural Circulation in a One-Dimensional Loop. Proc. of 2009 International Conference on Nuclear Engineering (ICONE17, 2009). American Society of Mechanical Engineers (ASME). Brussels, Belgium, 2009. CD-ROM.
- Benchmarking of thermal-hydraulic loop models for Lead-alloy-cooled advanced energy systems (LACANES). Phase 2: Natural convection. OECD/NEA, 2012.
- Moretti F., Lanfredini M., Mengali L., D’Auria F. Report sull’Accoppiamento di Codici CFD e Codice di Sistema. UNIPI-GRNSPG (CIRTEN). ADPFISS-LP2-075. Pisa, 2014.
- Tarantino M., Benardi D., Coccoluto G., Gaggini P., Labanti V., Forgione N., Napoli A. Natural and gas Enhanced circulation test in the NACIE Heavy Liquid Metal Loop. Proc. of ICONE, 18th International Conference on Nuclear Engineering. Xi'an, China, May 17–21, 2010, ICONE18-29969. Available at: https://www.researchgate.net/publication/317878038_ICONE23-2135_DESIGN_STATUS_OF_SMALL_MODULAR_REACTOR_COOLED_BY_LEAD-BISMUTH_EUTECTIC_NATURAL_CIRCULATION_URANUS (accessed 22.01.2026).
- Tarantino M. Gas Enhanced Circulation Experiments On Heavy Liquid Metal System. Report ENEA HS-F-R-001. 2007.
- Mitskevich A.V., Popov A.O., Gritsai A.S. Analiz zamykayushchih sootnosheniy po mezhfaznomu treniyu dlya system gas-ZhMT [Analysis of closure relations for calculating interphase friction in gas-LHMC systems]. Tehnologii obespecheniya zhiznennogo tsikla yadernyh energeticheskih ustanovok – Nuclear Propulsion Reactor Plants. Life Cycle Management Technologies, 2021, no. 3(25), pp. 9–22.
- Mitskevich A.V., Popov A.O., Gritsai A.S. Thermal-hydraulic model of the heavy liquid metal coolant – steam-water mixture flow. At Energy, 2025, issue 3–4, vol. 137, pp. 147–153. DOI: https://doi.org/10.1007/s10512-025-01188-x.
- Novitskiy P.V., Zograf I.A. Otsenka pogreshnostey rezultatov izmereniy [Uncertainty estimation of measurement results]. Leningrad: Energoatomizdat. Leningrad branch, 1985.
- Gricay A.S., Migrov Yu.A. Assessment of uncertainties of the models used in thermal–hydraulic computer codes. Therm. Eng., 2015, vol. 62, issue 9, pp. 656–662. DOI: https://doi.org/10.1134/S0040601515090049.
- Gmurman V.E. Teoriya veroyatnostei i matematicheskaya statistika: ucheb. posobie dlya vuzov [Theory of probability and mathematical statistics: textbook for universities]. Moscow, Vysshaya shkola Publ., 2003.
UDC 621.039.51
Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2026, no. 1, 1:19
