Калякин, Сергей Георгиевич: биография

3. Goverdovskii, A.A., Kalyakin, S.G. , Rachkov, V.I. The alternative strategies of the development of the nuclear power industry in the 21st century/Thermal Engineering (2014), Volume 61, Issue 5, pp 319–326, DOI: 10.1134/S0040601514050048

4. Rachkov, V.I., Kalyakin, S.G., Kukharchuk, O.F., Orlov, Yu.I., Sorokin, A.P. From the first nuclear power plant to fourth-generation nuclear power installations [on the 60th anniversary of the World's First nuclear power plant]/ Thermal Engineering (2014), Volume 61, Issue. 5, pp. 327–336 DOI: 10.1134/S0040601514050073

5. Rachkov, V.I., Arnol'Dov, M.N., Efanov, A.D., Kalyakin, S.G., Kozlov, F.A., Loginov, N.I., Orlov, Y.I., Sorokin, A.P. Use of liquid metals in nuclear and thermonuclear engineering, and in other innovative technologies/Thermal Engineering (2014), Volume 61, Issue 5, pp. 337–347 DOI: 10.1134/S0040601514050085

6. Alekseev, V.V., Kovalev, Yu.P., Kalyakin, S.G., Kozlov, F.A., Kumaev, V.Ya., Kondrat'Ev, A.S., Matyukhin, V.V., Pirogov, E.P., Sergeev, G.P., Sorokin, A.P., Torbenkova, I.Yu Sodium coolant purification systems for a nuclear power station equipped with a BN-1200 reactor/ Thermal Engineering (English translation of Teploenergetika) (2013) Volume 60, Issue 5 , pp. 311–322 DOI: 10.1134/S0040601513050017

7. В.И. Рачков, С.Г. Калякин. Инновационная ядерная энерготехнология - основа крупномасштабной ядерной энергетики.

8. В.И. Рачков, А.Д. Ефанов, А.В. Жуков, С.Г. Калякин, А.П. Сорокин. Теплогидравлические исследования ЯЭУ (к 60-летию пуска первой АЭС).

9. С.Г. Калякин, А.П. Сорокин, Ф.А. Козлов, В.В. Алексеев, С.И. Щербаков. Исследования в обоснование встроенной в бак реактора системы очистки натрия.

10. Д.Г. Зарюгин, С.Г. Калякин, С.Т. Лескин, А.Н. Опанасенко, А.П. Сорокин. Расчётно-экспериментальные исследования теплогидравлических характеристик в баке быстрого реактора на интегральной модели САРХ в различных режимах работы установки.

Публикации прошлых лет

1. Efanov, A.D., Kalyakin, S.G., Sorokin, A.P Thermophysical studies for validating new-generation nuclear-reactor designs/ Atomic Energy (2012) Volume 112, Issue 1, pp. 14–20 DOI: 10.1007/s10512-012-9518-5

2. Poplavksii, V.M., Efanov, A.D., Zhukov, A.V., Kalyakin, S.G., Sorokin, A.P., Yuriev, Y.S Thermohydraulic studies of sodium-cooled reactor facilities/ Atomic Energy, (2010) Volume 108, Issue 4, pp. 296–302 DOI: 10.1007/s10512-010-9292-1

3. Kopytov, I.I., Kalyakin, S.G., Berkovich, V.M., Morozov, A.V., Remizov, O.V. Experimental investigation of non-condensable gases effect on novovoronezh NPP-2 steam generator condensation power under the condition of passive safety systems operation/International Conference on Nuclear Engineering, Proceedings, ICONE Volume 2, 2009, pp. 735–743 DOI: 10.1115/ICONE17-75942

4. Efanov, A.D., Kalyakin, S.G., Morozov, A.V., Remizov, O.V., Tsyganok, A.A., Generalov, V.N., Berkovich, V.M., Taranov, G.S. Experimental investigation of non-condensable gases effect on operation of VVER steam generator in condensation mode/ International Conference on Advances in Nuclear Power Plants, ICAPP 2008, Volume 1, 2008, pp. 102–109

5. Efanov, A.D., Kalyakin, S.G., Morozov, A.V., Remizov, O.V., Tsyganok, A.A., Generalov, V.N., Berkovich, V.M., Taranov, G.S. Investigation of operation of VVER steam generator in condensation mode at the large-scale test rig/International Conference on Nuclear Engineering, Proceedings, ICONE, Volume 4, 2008, pp. 793–799 DOI: 10.1115/ICONE16-48842

6. Berkovich, V.M., Korshunov, A.S., Taranov, G.S., Kalyakin, S.G., Morozov, A.V., Remizov, O.V. Deelopment and validation of a technology for removal of noncondensing gases to ensure the operability of a passive heat removal system/Atomic Energy, Volume 100, Issue 1, (2006), pp. 14–19 DOI: 10.1007/s10512-006-0043-2

7. Kalyakin, S.G., Tsyganok, A.A., Taranov, G.S., Grigor'ev, M.M. Measurement of the characteristics of the ventilation pipe of the filtration system for the steam-gas medium of a nuclear power plant/ Atomnaya Energiya Volume 97, (2008) Issue 2, 2004, pp. 152–155

8. Kalyakin, S.G., Klimanova, Yu.V., Remizov, O.V., Serdun, N.P. Structure of a vapor-water flow and characteristic features of its separation in large-diameter channels/ Heat Transfer Research Volume 35, Issue 1-2, 2004, Pages 92–98 DOI: 10.1615/HeatTransRes.v35.i12.120

9. Kalyakin, S.G., Tsyganok, A.A., Taranov, G.S., Grigor'ev, M.M. Special features of steam-gas flow through a crack in the protective envelope of a nuclear power plant/ Atomnaya Energiya, Volume 97, Issue 5, 2004, Pages 333-338

10. Kalyakin, S.G., Tsyganok, A.A., Taranov, G.S., Grigor'ev, M.M. Special features of steam-gas flow through a crack in the protective envelope of a nuclear power plant/ Atomic Energy, Volume 97, Issue 5, November 2004, Pages 744-749 DOI: 10.1007/s10512-004-0002-8

11. Kalyakin, S.G., Tsyganok, A.A., Taranov, G.S., Grigor'ev, M.M. An experimental investigation of heat transfer in an air-to-air heat exchanger/ Teploenergetika, Issue 8, 2004, Pages 23–26

12. Kalyakin, S.G.a, Tsyganok, A.A.a, Taranov, G.S.b, Grigor'ev, M.M. An experimental investigation of heat transfer in an air-to-air heat exchanger/Thermal Engineering (English translation of Teploenergetika) Volume 51, Issue 8, August 2004, Pages 620-624

13. Kalyakin, S.G., Tsyganok, A.A., Taranov, G.S., Grigor'ev, M.M. Measurement of the characteristics of the ventilation pipe of the filtration system for the steam-gas medium of a nuclear power plant/Atomic Energy Volume 97, Issue 2, August 2004, Pages 583-586 DOI: 10.1023/B:ATEN.0000047686.31470.41

14. Bezlepkin, V.V., Kalyakin, S.G., Opanasenko, A.N. Stratified one- and two-phase flows in horizontal tubes and tank-tube systems/Atomnaya Energiya, Volume 95, Issue 2, 2003, Pages 98–102