Results 1 to 10 of about 774 (164)
Nuclear Engineering and Technology, 2016 Hydrogen release during severe accidents poses a serious threat to containment integrity. Mitigating procedures are necessary to prevent global or local explosions, especially in large steel shell containments.
Mehdi Dehjourian +4 more
doaj +3 more sources
Trudy Odesskogo Politehničeskogo Universiteta, 2020 The analysis of the known results of RELAP5/V.3.2 simulation for loss of coolant & blackout accidents at WWER nuclear power plants showed that the design accident management strategies with design passive safety systems do not provide the necessary ...
Володимир Іванович Скалозубов +5 more
doaj +5 more sources
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
doaj +1 more source
Modernized loss-of-coolant & blackout accident management strategy at nuclear power plants with wwer
Trudy Odesskogo Politehničeskogo Universiteta, 2020 The analysis of the known results of RELAP5/V.3.2 simulation for loss of coolant & blackout accidents at WWER nuclear power plants showed that the design accident management strategies with design passive safety systems do not provide the necessary ...
Володимир Іванович Скалозубов +5 more
doaj +5 more sources
LBLOCA accident investigation using TRACE code in a VVER-1000 reactor [PDF]
مجله علوم و فنون هستهای, 2020 The loss of coolant accident is due to the reduction of the coolant fluid volume in the first circuit. The direct cause of this accident is the mechanical failure or fatigue in the material of the first circuit components during the power plant operation.
S. Ekbatani-Amlashi +2 more
doaj +1 more source
Transient calculation on TRIGA 2000 of plate-type fuel element using RELAP5, EUREKA2/RR, and MTR-DYN codes [PDF]
Nuclear Technology and Radiation Protection, 2021 The TRIGA 2000 reactor Bandung is proposed to convert from rod-type fuel to plate-type fuel because there are no manufacturers in the world that still produce rod-type fuel.
Dibyo Sukmanto +2 more
doaj +1 more source
Analysis of thermal hydraulic behavior of KONVOI PWR during a design extension condition [PDF]
Nuclear Technology and Radiation Protection, 2021 In nuclear power plants the design extension conditions are more complex and severe than those postulated as design basis accidents, therefore, they must be taken into account in the safety analyses.
Helmy Salwa, Kandil Magy, Refaey Ahmed
doaj +1 more source
Safety Researches on LWR Loss-of-Coolant Accident [PDF]
Journal of Nuclear Science and Technology, 1989 On the LWR LOCA safety, many experimental and analytical works were performed in the governmental organization and the nuclear industries. The works covers not only LOCA ECCS studies but also studies on containment spray, hydrogen diffusion in the containment, pressure suppression and pipe behavior.
SATO, Kazuo +2 more
openaire +1 more source
The sensitivity analysis for APR1400 nodalization under Large Break LOCA condition based on mars code [PDF]
Nuclear Technology and Radiation Protection, 2017 The phenomena of loss of coolant accident have been investigated for long time and the result of experiment shows that the flow condition in the downcomer during the end-of-blowdown were highly multi-dimensional at full-scale.
Jang Hyung-Wook +3 more
doaj +1 more source
Design and implementation of cloud platform for nuclear accident simulation
Frontiers in Energy Research, 2023 Introduction: To meet the multi-user, cross-time-and-space, cross-platform online demand of work, and professional training teaching in nuclear reactor safety analysis under the normalization of Coronavirus Disease 2019.Method: Taking the nuclear ...
Pengyu Chen +8 more
doaj +1 more source