Results 21 to 30 of about 4,286 (261)
Thermohydraulic studies of alkali liquid metal coolants for justification of nuclear power facilities [PDF]
Nuclear Energy and Technology, 2022 The paper presents and discusses the results of experimental and computational studies obtained by the authors on hydrodynamics and heat exchange in fuel assemblies of the alkali liquid metal cooled fast reactor cores, and experimental data on ...
Yulia A. Kuzina +4 more
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Hydraulic transients for loss of coolant accidents [PDF]
, 1986 This paper discusses calculations related to hydraulics in a loss of coolant reactor accident. Earlier calculations ignored the effect of emergency coolant injection. Present results show that if the ECS flow is considered, reactor coolant flow is maintained for much longer periods.
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Evaluation of weight of coolant in the reactor plant during full loss of feeding coolant
Technology audit and production reserves, 2013 Исследуется и предлагается новый метод определения массы пароводяной смеси в водо-водяном энергетическом реакторе в аварийных режимах, а именно сравнение ранее полученных значений по взвешиванию реактора со всеми внутрикорпусными устройствами и теплоносителем в нормальном режиме эксплуатации с новыми значениями из-за изменения рабочих давления и ...
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Validation of Advanced Computer Codes for VVER Technology: LB-LOCA Transient in PSB-VVER Facility
Science and Technology of Nuclear Installations, 2012 The OECD/NEA PSB-VVER project provided unique and useful experimental data for code validation from PSB-VVER test facility. This facility represents the scaled-down layout of the Russian-designed pressurized water reactor, namely, VVER-1000.
A. Del Nevo +8 more
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Nuclear Engineering and Technology, 2020 Numerical prediction of fission product plateout and circulating coolant activities under normal operating conditions is crucial in the design of a high temperature gas-cooled reactor (HTGR).
Nam-il Tak +3 more
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Loss of coolant accident analysis under restriction of reverse flow
Nuclear Engineering and Technology, 2019 This paper analyzes a new method for reducing boiling water reactor fuel temperature during a Loss of Coolant Accident (LOCA). The method uses a device called Reverse Flow Restriction Device (RFRD) at the inlet of fuel bundles in the core to prevent ...
Majdi I. Radaideh +2 more
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Nuclear Engineering and Technology, 2018 An experiment was performed using the large-scale test facility (LSTF), which simulated a 1% vessel upper head small-break loss-of-coolant accident with an accident management (AM) measure under an assumption of total-failure of high-pressure injection ...
Takeshi Takeda
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Tolerant Fuel for WWER-1200 Reactors with High Thermal Conductivity
Глобальная ядерная безопасность, 2022 The main factor of destruction of fuel rods in accidents with loss of coolant is associated with the vapor-zirconium reaction occurring between the fuel rod shell and the coolant (water).
A. Z. Alhmoud +2 more
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Journal of Nuclear Engineering, 2023 This paper presents the results obtained from numerical evaluations for the possibility of large-scale 238Pu production in the light-water VVER-1000 reactor and the reactivity effect caused by the loss-of-coolant accident in the central fuel assembly of ...
Anatoly N. Shmelev +5 more
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ANALYSIS OF SPENT FUEL POOL LOSS OF COOLANT INVENTORY ACCIDENT PROGRESSION
Journal of Energy : Energija, 2022 The Spent Fuel Pool (SFP) in a nuclear power plant is a robust structure designed to withstand large seismic loads. After the terrorist attacks on September 11 and the accident in the Fukushima nuclear power plant, special attention was focused on safety assessments and taking measures to mitigate possible accidents related to the spent fuel pool. This
ĐAKOVIĆ, JOSIP, GRGIĆ, DAVOR
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