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Matrices for verification of best estimate thermohydraulic codes annlied to VVER reactors

Author
BEZRUKOV, Yu. A1 ; LOGVINOV, S. A1 ; SUSLOV, A. I2 ; SOLOV'EV, S. L3
[1] Special Design Bureau (OKB) Gidropress, ul. Ordzhonikidze 21, Podol'sk, Moscow oblast, 142103, Russian Federation
[2] The Russian Research Center Kurchatov Institute, Moscow, 107113, Russian Federation
[3] Branch Center of Computation Codes (OTsRK), Ministry of Nuclear Power Engineering (Minatom) of Russia, ul. Malaya Krasnosel'skaya 2/8, Moscow, 107113, Russian Federation
Source

Thermal engineering. 2002, Vol 49, Num 11, pp 922-928, 7 p ; ref : 6 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)
Code calcul Réacteur eau pressurisée Réacteur nucléaire Simulation ordinateur Système refroidissement Sécurité réacteur fission Thermohydraulique Réacteur VVER
Keyword (en)
Computation code Pressurized water reactor Nuclear reactor Computer simulation Cooling system Fission reactor safety Thermohydraulics
Keyword (es)
Código computación Reactor agua a presión Reactor nuclear Simulación computadora Sistema enfriamiento Termohidraúlica
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
14384102

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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