DOI: 10.55176/2414-1038-2021-3-158-166
Authors & Affiliations
Loginov N.I., Mikheyev A.S., Vereshchagina T.N.
A.I. Leypunsky Institute for Physics and Power Engineering, Obninsk, Russia
Loginov N.I. – Chief Researcher, Dr. Sci. (Techn). Contacts: 1, pl. Bondarenko, Obninsk, Kaluga region, Russia, 249033. Tel.: +7 (484) 399-85-55; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Mikheyev F.S. – Senior Researcher.
Vereshchagina T.N. – Chief Researcher, Dr. Sci. (Techn.).
Abstract
The article discusses the designs of two nuclear reactors cooled by heat pipes with liquid metal coolants. Both designs were developed at IPPE JSC. The first design is a research reactor with a capacity of 1.2 MW. Evaporating sodium is used as a coolant in the core. The evaporating eutectic sodium-potassium alloy is used as a coolant in the secondary loop. The third loop contains gas as working fluid of the Stirling or Brighton cycle. The report presents the results of thermo-hydraulic experiments that confirmed the main design parameters.
The second design called RIFMA is an innovative super small NPP with direct conversion of thermal energy into electricity and is supposed, in particular, to be used in the Arctic region. Thermal power is 100 kW, efficiency is not less than 10 %. Molybdenum heat pipes filled with lithium are used to transfer heat from the core. To convert energy, thermophotovoltaic converters are proposed. They are cooled by low-temperature heat pipes that remove residual heat and transfer it to air radiators. A nuclear power plant concept and three versions of the core are presented.
Keywords
heat pipe, nuclear power plant, coolant, liquid metal, core, sector model, thermo-hydraulic experiments, direct energy conversion, thermophotovoltaic
Article Text (PDF, in Russian)
References
- Grover G.M. Evaporation-condensation Heat Transfer Device. Patent US, no. 3229759, 1966.
- Ivanovsky M.N., Sorokin V.P., Yagodkin I.V. Fizicheskie osnovy teplovykh trub [Physical Basis of Heat Pipes]. Moscow, 1978. 256 p.
- Ivanovsky M.N., Sorokin V.P., Yagodkin I.V., Chulkov B.A. Tekhnologicheskieosnovyteplovykhtrub. [The Technological Basis of the Heat Pipes]. Moscow, Atomizdat Publ., 1980. 160 p.
- Loginov N., Mikheyev A., Chulkov B. et al. Heat Pipes for Thermionic Energy Converters (TEC). Preprints of 8th International Heat Pipe Conference. China, 1992, E-P52.
- Bezrodniy M.K., Pioro I.L., Kostyuk T.O. Protsessy teplomassoobmena v dvukhfaznykh termosifonnykh sistemakh [Transfer Processes in the Two-phase Thermosyphon Systems]. Kiev, FAKT Publ., 2005. 704 p.
- Loginov N., Mikheyev A. On Concept of Heat-pipe Emergency Core Cooling System for Fast Sodium Fission Reactors. Proc. 12th International Heat Pipe Conference. Moscow-Kostroma-Moscow, 2002, pp. 444–447.
- Jarygin V.I., Kuptsov G.A., Ionkin V.I. et al. Termoemissionnyy elektrogeneriruyushchiy modul' dlya aktivnoy zony yadernogo reaktora s vynesennoy termoemissionnoy sistemoy preobrazovaniya teplovoy energii v elektricheskuyu (varianty) [Thermionic power-generating module for nuclear reactor core and external thermionic heat-to-power conversion system (alternatives)]. Patent RU, no. 2187156, 2002.
- El-Genk M.S. Space Reactor Power Systems with no Single Point Failures. Journal Engineering and Design, 2008, vol. 238, issue 9, pp. 2245–2255.
- Sabharwall P., Gannerson, F. Engineering Design Elements of Two-Phase Thermosyphon for the Purpuse of Transfering NGNP Thermal Energy to a Hydrogen Plant. Nuclear Engineering and Design, 2009, vol. 239, issue 11, pp. 2293–2301.
- Zasorin I.I., Ivanovskij M.N., Loginov N.I. et al. Sposob izgotovleniya teploobmennogo oborudovaniya s zhidkometallicheskim teplonositelem [Method of manufacture of heat-exchange equipment with liquid-metal heat-transfer agent]. Patent RU, no. 2175102, 2001.
- Berensky L.L., Ivanovsky M.N., Loginov N.I. et al. O vliyanii dispersnoy fazy na poverkhnostnoe natyazhenie natriya [The effect of dispersed phase on the surface tension of sodium]. Teplofizika vysokikh temperatur – High Temperature, 1997, vol. 35, no. 2, pp. 346–348.
- Mcclure P.R. et al. Mobile Heat Pipe Cooled Fast Reactor System. Patent US, no. 10643756, 2020.
- Loginov N.I., Pyshko A.P., Mikheev A.S., Denezhkin I.A. Yadernyy reaktor s pryamym preobrazovaniem energii za predelami aktivnoy zony [Nuclear reactor with direct transformation of energy outside the active zone]. Patent RU, no. 2650885, 2018.
- Loginov N.I., Krotov A.D., Mikheev A.S. Aktivnaya zona yadernogo reaktora [Active zone of the nuclear reactor]. Patent RU, no. 2660942, 2018.
- Gibson M., Poston D., Mcclure P.R., Godfroy T., Sanzi J., Briggis M.H. The Kilopower Reactor Using Stirling TechnologY (KRUSTY) Nuclear Ground Test Results and Lessons Learned. Proc. 2018th International Energy Conversion Engineering Conference. Cincinnati, USA, 2018,AIAA 2018-4973. DOI: https://doi.org/10.2514/6.2018-4973.
UDC 621.039.52.034.6
Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2021, issue 3, 3:12
