An experimental study of heat transfer in the core of a BREST-OD-300 reactor with lead cooling on models
- Author
- ZHUKOV, A. V1 ; KUZINA, Yu. A1 ; SOROKIN, A. P1 ; LEONOV, V. N2 ; SMIRNOV, V. P2 ; SILA-NOVITSKII, A. G2
[1] State Scientific Center of the Russian Federation, the Physics-Energy Institute (GNTs RF FEI), pl. Bondarenko 1, Obninsk, Kaluzhskaya oblast, 249033, Russian Federation
[2] Power Engineering R&D Institute (NIKIET), Russian Federation - Source
Thermal engineering. 2002, Vol 49, Num 3, pp 175-184 ; ref : 18 ref
- ISSN
- 0040-6015
- Scientific domain
- Energy; Mechanical engineering; Metallurgy, welding
- Publisher
- Springer, New York, NY
- Publication country
- United States
- Document type
- Article
- Language
- Russian
- Keyword (fr)
- Coeur réacteur Essai sur modèle Etude expérimentale Plomb Réacteur nucléaire Réacteur rapide Réacteur refroidi métal liquide Thermohydraulique Transfert chaleur
- Keyword (en)
- Reactor core Model test Experimental study Lead Nuclear reactor Fast reactor Liquid metal cooled reactors Thermohydraulics Heat transfer
- Keyword (es)
- Núcleo reactor Ensayo sobre modelo Estudio experimental Plomo Reactor nuclear Reactor rápido Termohidraúlica Transferencia térmica
- Classification
- Pascal
- 001 Exact sciences and technology / 001D Applied sciences / 001D06 Energy / 001D06D Energy. Thermal use of fuels / 001D06D04 Installations for energy generation and conversion: thermal and electrical energy. / 001D06D04D Fission nuclear power plants
- Discipline
- Energy
- Origin
- Inist-CNRS
- Database
- PASCAL
- INIST identifier
- 13599325
Sauf mention contraire ci-dessus, le contenu de cette notice bibliographique peut être utilisé dans le cadre d’une licence CC BY 4.0 Inist-CNRS / Unless otherwise stated above, the content of this bibliographic record may be used under a CC BY 4.0 licence by Inist-CNRS / A menos que se haya señalado antes, el contenido de este registro bibliográfico puede ser utilizado al amparo de una licencia CC BY 4.0 Inist-CNRS
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