Station Black-Out Analysis with MELCOR 1.8.6 Code for Atucha 2 Nuclear Power Plant

Uncertainty Analyses Using the MELCOR Severe Accident Analysis Code

The MELCOR code is a detailed system level computer code capable of performing integrated selfconsistent analyses of severe accident progression in commercial nuclear power plants, supporting level 2 probablilistic risk assessment (PRA) studies. Originally developed as a fast running tool with simplified models for performing probabilistic safety analyses and sensitivity studies, MELCOR now emp...

Nuclear Power Plant Safety

In the last decade nuclear reactors have proven to be a source of electrical energy economically competitive with conventional means of power production. With the resulting increase in orders for nuclear power stations there has been a corresponding increase in public awareness of the safety and environmental aspects of these facilities. This public awareness has been evidenced by the number of...

Fukushima nuclear power plant area

High-resolution tomographic images of the crust and upper mantle in and around the area of the 2011 Iwaki earthquake (M 7.0) and the Fukushima nuclear power plant are determined by inverting a large number of high-quality arrival times with both the finite-frequency and ray tomography methods. The Iwaki earthquake and its aftershocks mainly occurred in a boundary zone with strong variations in ...

Time Out for Station Identification

Bayesian analysis and decisions in nuclear power plant maintenance

It is somewhat true that in most mainstream statistical literature the transition from inference to a formal decision model is seldom explicitly considered. Since the Markov chain Monte Carlo (MCMC) revolution in Bayesian statistics, focus has generally been on the development of novel algorithmic methods to enable comprehensive inference in a variety of applications, or to tackle realistic pro...