1 documents found
Information × Registration Number 0215U008307, 0113U001969 , R & D reports Title Optimization of thermohydraulic characteristics of heat exchanging and steam generating equipment for fourth generation high temperature gas cooled nuclear power plant of 250 MWt thermal power popup.stage_title Head Khalatov Artem Artemovich, Registration Date 24-12-2015 Organization Institute of Engineering Thermophysics of the Ukrainian National Academy of Sciences popup.description2 The technique of thermal hydraulic calculation of the high temperature steam generator of NPP of GT-MHR-HTE type is given and the mathematical model of the nuclear steam generator of AES vertical-type with helical coil tubes is developed on its basis. Using a steam generator mathematical model the conceptual methodology of multi-criterial optimization of thermal-hydraulic and mass-dimensional characteristics of a nuclear steam generator of AES with high-temperature gas-cooled reactors using helium as the primary heat-transfer agent was developed. Product Description popup.authors Борисов І.І. Дворянська О.А. Доник Т.В. Кобзар С.Г. Коваленко Г.В. Коваленко О.С. Лісовський О.В. Педаш І.Р. Присекіна Є.А. Сєвєрін С.Д. Шіхабутінова О.В. Шевцов С.Д. popup.nrat_date 2020-04-02 Close
R & D report
Head: Khalatov Artem Artemovich. Optimization of thermohydraulic characteristics of heat exchanging and steam generating equipment for fourth generation high temperature gas cooled nuclear power plant of 250 MWt thermal power. (popup.stage: ). Institute of Engineering Thermophysics of the Ukrainian National Academy of Sciences. № 0215U008307
1 documents found

Updated: 2026-03-22