Results 51 to 60 of about 75,931 (208)
A comprehensive review on the technical standards about human factors (HF) design and software reliability maintenance for digital instrumentation and control (I&C) and human-machine interface technology (HMIT) in Japanese light water reactor nuclear ...
HIDEKAZU YOSHIKAWA
doaj +1 more source
A review of COHRISK: Multihazard risk quantification software for nuclear power plants
A combination of more than one natural hazard can occur simultaneously by their inherent correlation or by coincidence. One well-known multihazard incident, the Tohoku earthquake-tsunami in Japan 2011, led to a core damage accident at the Fukushima ...
Eujeong Choi +5 more
doaj +1 more source
This paper analyzes the methods and technologies for assessing the method of formation, composition, characteristics and features of corium, which is a mixture of nuclear and structural materials of the nuclear reactor core, formed as a result of an ...
S. N. Ryzhov +6 more
doaj +1 more source
The Fukushima Daiichi NPP Accident, Its After Effects And The Lessons Learnt From It
A tsunami induced by an earthquake of magnitude nine hit the Fukushima Daiichi NPP on 11th March, 2011. A seawall of only 10 m high above sea level against tsunami waves of 15 m, led to a series of catastrophic events like inundation of the backup diesel generators exceptionally located at the basement, hydrogen explosions at three units etc. Immediate
Md Akhlak Bin Aziz +3 more
openaire +2 more sources
SYSTEM DYNAMICS MODEL DEVELOPMENT BY ANALYZING CAUSES OF FUKUSHIMA DAIICHI NPP UNIT-1 ACCIDENT
— Fukushima Daiichi NPP accident occurred on March 11, 2011. A system dynamics model is developed by analyzing the chronological progression and causes of the Fukushima Daiichi NPP unit-1 accident applying causeeffect relationship and qualitative causal loop and feedback loop.
Muhammed Mufazzal Hossen, Mahmud Hossain
openaire +1 more source
Time‐Series Forecasting of a Typical PWR Undergoing Large Break LOCA
In this work, a machine learning (ML) metamodel is developed for the time‐series forecasting of a typical nuclear power plant response undergoing a loss of coolant accident (LOCA). The plant model of choice is based on the APR1400 nuclear reactor. The key systems and components of APR1400 relevant to the investigated scenario are modelled using the ...
Michal Kaminski +2 more
wiley +1 more source
Enhancing Resilience through Nuclear Emergency Preparedness at El Dabaa Site
The research utilized advanced PCTRAN and RASCAL software to evaluate the potential radiological impacts of hypothetical accidents, specifically loss‐of‐coolant accident (LOCA) and long‐term station blackout (LTSBO), at the El Dabaa Nuclear Power Plant. Over a span of ten years, comprehensive meteorological data were meticulously analyzed to assess the
Waad Saleh, Juyoul Kim, Doddy Kastanya
wiley +1 more source
The accident at the Fukushima Daiichi Nuclear Power Plant (NPP) in Japan resulted in the release of a large number of fission products that were transported worldwide.
Nikolaos Evangeliou +3 more
doaj +1 more source
Analysis of Ex‐Vessel Debris Coolability of Boiling Water Reactors
To evaluate the effectiveness of the wet cavity strategy, the authors developed a stochastic evaluation method that considers the uncertainties of the molten material conditions ejected from reactor pressure vessels. This study analyzed the probability of ex‐vessel debris coolability under the wet cavity strategy.
Toshinori Matsumoto +3 more
wiley +1 more source
Tsunami inundation modeling method NPP industrial site in Fukushima-daiichi
Предложена гидродинамическая модель возникновения и распространения цунами на основе консервативных допущений. В результате численного моделирования установлена возможность достижения высоты волны 15 м у побережья АЭС Fukushima-Daiichi при значении ...
Драган, Г.С. +4 more
core +1 more source

