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Kozlov, F. A., Ivanenko, V. N. (1996) Sodium — Coolant for nuclear power plants with fast reactors. Atomic Energy, 80 (5) 318-324 doi:10.1007/bf02418710

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Reference TypeJournal (article/letter/editorial)
TitleSodium — Coolant for nuclear power plants with fast reactors
JournalAtomic Energy
AuthorsKozlov, F. A.Author
Ivanenko, V. N.Author
Year1996 (May)Volume80
Issue5
PublisherSpringer Science and Business Media LLC
DOIdoi:10.1007/bf02418710Search in ResearchGate
Generate Citation Formats
Mindat Ref. ID12891323Long-form Identifiermindat:1:5:12891323:1
GUID0
Full ReferenceKozlov, F. A., Ivanenko, V. N. (1996) Sodium — Coolant for nuclear power plants with fast reactors. Atomic Energy, 80 (5) 318-324 doi:10.1007/bf02418710
Plain TextKozlov, F. A., Ivanenko, V. N. (1996) Sodium — Coolant for nuclear power plants with fast reactors. Atomic Energy, 80 (5) 318-324 doi:10.1007/bf02418710
In(1996, May) Atomic Energy Vol. 80 (5) Springer Science and Business Media LLC

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Kozlov, F. A., Alekseev, V. V., Sorokin, A. P. (2014) Development of Sodium Coolant Technology for Fast Reactors. Atomic Energy, 116 (4) 278-284 doi:10.1007/s10512-014-9854-8
Gromov, B. F., Orlov, Yu. I., Toshinskii, G. I., Chekunov, V. V. (1996) Nuclear power plants with Lead-Bismuth Coolant. Atomic Energy, 81 (5) 770-775 doi:10.1007/bf02408176
Poplavskii, V. M., Efanov, A. D., Kozlov, F. A., Sorokin, A. P., Korolkov, A. S., Shtynda, Yu. E. (2010) Sodium as a coolant for fast reactors. Atomic Energy, 108 (4) 281-288 doi:10.1007/s10512-010-9290-3
Kozlov, F. A., Bogdanovich, N. G., Zagorulko, Yu. I., Matveev, V. P. (2012) Sodium coolant for fast reactors: experience in preparation and delivery to BN-600; problems for BN-800. Atomic Energy, 112 (4) 235-240 doi:10.1007/s10512-012-9551-4
Pupko, V. Ya. (1996) Work on nuclear power plants for space. Atomic Energy, 80 (5) 335-338 doi:10.1007/bf02418713
Kozlov, F. A., Alekseev, V. V. (1996) The theoretical basis for purifying sodium from tritium. Atomic Energy, 80 (4) 284-287 doi:10.1007/bf02419310
Kozlov, F. A., Alekseev, V. V. (1990) Influence of engineering parameters on tritium transport in sodium-cooled fast reactors. Soviet Atomic Energy, 68. 107-112 doi:10.1007/bf02069868
Voronin, L. M., Volkov, A. P., Kozlov, V. F., Luzanova, L. M., Pashevich, V. I. (1979) Activity of radionuclides in the coolant of the secondary loop of a nuclear power plant with VV�R-440 reactors. Soviet Atomic Energy, 46. 31-35 doi:10.1007/bf01119948
Baklushin, R. P., Kozlov, F. A. (1978) Sodium-purification systems for primary and secondary loops of fast reactors. Soviet Atomic Energy, 44. 248-252 doi:10.1007/bf01117629
Titov, V. F. (1994) Steam generators of the power-generating units of nuclear power plants with VVÉR-1000 reactors. Atomic Energy, 77 (2) 588-595 doi:10.1007/bf02407431
Sorokin, A. P., Kalyakin, S. G., Kozlov, F. A., Alekseev, V. V., Bogoslovskaya, G. P., Ivanov, A. P., Konovalov, M. A., Morozov, A. V., Orlova, E. A., Stogov, V. Yu. (2014) High-Temperature Nuclear Energy Technology Based on Sodium-Cooled Fast Reactors for Hydrogen Production. Atomic Energy, 116 (4) 241-251 doi:10.1007/s10512-014-9849-5
 
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