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Thermal hydraulic analysis and estimation of hydrogen generation in severe accidents in WWER1000 [PDF]
مجله علوم و فنون هستهای, 2022 Severe Accidents Management (SAM) in nuclear power plants is an important safety issue. SAMs require assessing the thermal-hydraulic conditions of the nuclear reactor during the accident.
R. Gharari +4 more
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Accident occurrence frequency of a small helium-xenon gas cooled nuclear reactor system
He jishu, 2022 BackgroundHelium-xenon gas cooled nuclear reactor adopts helium-xenon gas as the coolant and is able to apply the integral Brayton cycle. It has advantages in miniaturization and lightweight design, which has attracted more and more attention worldwide ...
WU Jianhui +6 more
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“Practical elimination” principle in the Akkuyu Nuclear Power Plant design [PDF]
Nuclear Energy and Technology, 2023 The paper considers the implementation of the “practical elimination” principle in the design of the Akkuyu NPP with VVER1200 reactors being under construction in Turkey. The “practical elimination” principle is defined as follows: for accident sequences
Artur V. Lyubarskiy +2 more
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Simulation of Partial and Complete Loss of Flow Accidents for GPWR using ATHLET Code
International Journal of Thermofluids, 2021 In Nuclear power plants, simulation of the thermal hydraulic systems at loss of flow, accidents is commonly used to perform safety and licensing analyses through regulatory and safety authorities since they are considered as design base accidents.
Salwa H. Abdel-Latif +3 more
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Review of accident analyses of RB experimental reactor [PDF]
Nuclear Technology and Radiation Protection, 2003 The RB reactor is a uranium fuel heavy water moderated critical assembly that has been put and kept in operation by the VTNCA Institute of Nuclear Sciences, Belgrade, Serbia and Montenegro, since April 1958.
Pešić Milan P.
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Energies, 2021 Nuclear power is a major source of electricity in the international community. However, a significant problem with nuclear power is that, if a severe nuclear accident occurs, radiation may leak and cause great damage.
Sang-Hyun Park +2 more
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The CABRI fast neutrons Hodoscope: CABRI model and signal-to-mass conversion charts [PDF]
EPJ Web of Conferences, 2023 The CABRI experimental pulse reactor, located at the Cadarache nuclear research center, southern France, is devoted to the study of Reactivity Initiated Accidents (RIA).
Chevalier Vincent, Di Salvo Jacques
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A Preliminary Safety Analysis for the Prototype Gen IV Sodium-Cooled Fast Reactor
Nuclear Engineering and Technology, 2016 Korea Atomic Energy Research Institute has been developing a pool-type sodium-cooled fast reactor of the Prototype Gen-IV Sodium-cooled Fast Reactor (PGSFR).
Kwi Lim Lee +9 more
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Frontiers in Energy Research, 2018 Interest in evaluation of reactor response and off-site consequences following beyond design basis accidents has significantly increased after Fukushima.
Shasha Yin +6 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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