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pro vyhledávání: '"Vladimir I. Nalivayev"'
Autor:
Alexander D. Vasiliev, Valerii F. Strizhov, Vladimir I. Nalivayev, Nikolay Ya. Parshin, Arcadii E. Kisselev
Publikováno v:
Volume 3: Thermal Hydraulics; Current Advanced Reactors: Plant Design, Construction, Workforce and Public Acceptance.
The PARAMETER-SF3 test conditions simulated a severe LOCA (Loss of Coolant Accident) nuclear power plant sequence in which the overheated up to 1700÷2300K core would be reflooded from the top and the bottom in occasion of ECCS (Emergency Core Coolin