Results 1 to 10 of about 583,056 (308)
Nuclear Materials and Energy, 2022 Cs-bearing microparticles, released during the accident of Fukushima Daiichi, are a significant concern for health and environment due to their abundance over wide areas, associated with a low solubility.
Hugo Laffolley +4 more
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International Journal of Advanced Nuclear Reactor Design and Technology, 2023 Ex-vessel melt Retention (EVR) is one of the important countermeasures to address the issue of basement melt penetration in the course of a hypothetical severe accident in a nuclear power plant.
Nan Li +5 more
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Applied Sciences, 2023 Steam condensation plays an important role in various engineering processes due to its excellent heat transfer performance. However, condensation in the presence of noncondensable gas has attracted great attention in recent years since noncondensable gas
He Li +5 more
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International Journal on Cybernetics & Informatics, 2023 Road accidents have significant economic and societal costs, with a small number of severe accidents accounting for a large portion of these costs. Predicting accident severity can help in the proactive approach to road safety by identifying potential unsafe road conditions and taking well-informed actions to reduce the number of severe accidents. This
Adefabi, Adekunle +5 more
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MELCOR steady state calculation of the generic PWR of 40MWth
Brazilian Journal of Radiation Sciences, 2021 After the two most significant nuclear accidents in history – the Chernobyl Reactor Four explosion in Ukraine (1986) and the Fukushima Daiichi accident in Japan (2011) –, the Final Safety Analysis Report (FSAR) included a new chapter (19) dedicated to ...
Maritza Rodríguez Gual +2 more
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MODELING LOFW IN A PWR USING MELCOR
Brazilian Journal of Radiation Sciences, 2021 The Probabilistic Safety Assessment (PSA) is part of a Nuclear Power Plant (NPP) licensing process. It considers the elaboration and updating of probabilistic models that estimate the risk associated to the operation, allowing the risk monitoring from ...
Maritza Rodríguez Gual +3 more
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NUMERICAL INVESTIGATION OF THE SPREADING AND HEAT TRANSFER CHARACTERISTICS OF EX-VESSEL CORE MELT
Nuclear Engineering and Technology, 2013 The flow and heat transfer characteristics of the ex-vessel core melt (corium) were investigated using a commercial CFD code along with the experimental data on the spreading of corium available in the literature (VULCANO VE-U7 test).
IN-SOO YE +5 more
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Assessment of the severe accident code MIDAC based on FROMA, QUENCH-06&16 experiments
Nuclear Engineering and Technology, 2022 In order to meet the needs of domestic reactor severe accident analysis program, a MIDAC (Module In-vessel Degraded severe accident Analysis Code) is developed and maintained by Xi'an Jiaotong University. As the accuracy of the calculation results of the
Shihao Wu +5 more
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Applied Sciences, 2022 In nuclear power plants, a severe accident is a critical accident involving significant nuclear core damage and it is managed by using a set of Severe Accident Management Guidelines (SAMG).
Shelly Salim, Eun-Bi Choi, Dong-Han Ham
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Factors influencing accident severity: an analysis by road accident type
Transportation Research Procedia, 2020 Abstract Nowadays, road safety is an issue particularly relevant because of the increasing occurrence of road accidents. For this reason, it is very important to analyze accident severity and the factors influencing it. This paper aims to investigate on the characteristics that can influence the severity of an accident by distinguishing between the ...
Eboli L., Forciniti C., Mazzulla G.
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