HEAT EXCHANGE CONDITIONS IN THE DRY STORAGE CONTAINER FOR SPENT NUCLEAR FUEL OF POWER REACTORS
Elektrotehnìka ta Elektroenergetika, 2018 Purpose. The safety substantiation of the spent nuclear fuel of power reactors WWER-1000 of Zaporizhska NPP dry storage facility operation by carrying out of numerical study of the thermal processes inside dry storage container. Methodology. Mathematical
S.V. Alyokhina
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Fuel element cladding state change mathematical model for a WWER-1000 plant operated in the mode of varying loading [PDF]
Ядерна фізика та енергетика, 2010 Main features of a fuel element cladding state change mathematical model for a WWER-1000 reactor plant operated in the mode of varying loading are listed.
S. N. Pelykh
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Весці Нацыянальнай акадэміі навук Беларусі: Серыя фізіка-тэхнічных навук, 2020 The article presents the results of computational modeling of the development of accidents in the containment of NPP with water-water energy reactor (WWER) using the COCOSYS software.
D. L. Tretinnikov +2 more
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Trudy Odesskogo Politehničeskogo UniversitetaA deterministic method has been developed to determine the conditions and consequences of steam explosions during complete power outages accidents with inter circuit leaks at nuclear power plants with WWER/PWR reactors. The required conditions for steam
Володимир Іванович Скалозубов +4 more
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THE ASSESSMENT OF SAFETY SYSTEMS IN WWER-1000 NUCLEAR REACTOR USING IAEA SIMULATOR
Tạp chí Khoa học Đại học Đà Lạt, 2017 In this study, the operation and response capability of safety system in nuclear reactor WWER-1000 was analyzed during the accidents that involved the failure of main circulation pump or feed water pumps. The nuclear reactor WWER-1000 simulator developed
Trần Đăng Khoa +1 more
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Long-Term Oxidation of Zirconium Alloy in Simulated Nuclear Reactor Primary Coolant-Experiments and Modeling. [PDF]
Materials (Basel), 2023 Betova I, Bojinov M, Karastoyanov V.
europepmc +1 more source
Welch-weighted Egger regression reduces false positives due to correlated pleiotropy in Mendelian randomization. [PDF]
Am J Hum Genet, 2021 Brown BC, Knowles DA.
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Investigation of Stress Corrosion Cracking Resistance of Irradiated 12Cr Ferritic-Martensitic Stainless Steel in Supercritical Water Environment. [PDF]
Materials (Basel), 2023 Margolin B +5 more
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Removal of Cs-137 Radionuclide by Resorcinol-Formaldehyde Ion-Exchange Resins from Solutions Simulating Real Liquid Radioactive Waste. [PDF]
Molecules, 2022 Tokar E, Tutov M, Bratskaya S, Egorin A.
europepmc +1 more source
Magnetic Investigation of Cladded Nuclear Reactor Blocks. [PDF]
Materials (Basel), 2022 Vértesy G +3 more
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