Results 1 to 10 of about 205,528 (262)
SEVERE ACCIDENT ISSUES RAISED BY THE FUKUSHIMA ACCIDENT AND IMPROVEMENTS SUGGESTED
Nuclear Engineering and Technology, 2014 This paper revisits the Fukushima accident to draw lessons in the aspect of nuclear safety considering the fact that the Fukushima accident resulted in core damage for three nuclear power plants simultaneously and that there is a high possibility of a ...
JIN HO SONG, TAE WOON KIM
doaj +3 more sources
Prediction of severe accident occurrence time using support vector machines
Nuclear Engineering and Technology, 2015 If a transient occurs in a nuclear power plant (NPP), operators will try to protect the NPP by estimating the kind of abnormality and mitigating it based on recommended procedures.
Seung Geun Kim +2 more
doaj +3 more sources
Perspectives on a Severe Accident Consequences—10 Years after the Fukushima Accident
Journal of Nuclear Engineering, 2021 Scientific issues that draw international attention from the public and experts during the last 10 years after the Fukushima accident are discussed. An assessment of current severe accident analysis methodology, impact on the views of nuclear reactor ...
Jinho Song
doaj +3 more sources
Nuclear Engineering and Technology, 2022 Integrated severe accident codes should be capable of simulating not only specific physical phenomena but also entire plant behaviors, and in a sufficiently fast time. However, significant uncertainty may exist owing to the numerous parametric models and
Wonjun Choi +2 more
doaj +3 more sources
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
doaj +1 more source
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
doaj +1 more source
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
doaj +1 more source
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
doaj +1 more source
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
doaj +1 more source
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
doaj +1 more source