NPP Krško Station Blackout Analysis after Safety Upgrade Using MELCOR Code

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...

NPP Safety Automation Systems Analysis. State of the Art

Modeling of a Flooding Induced Station Blackout for a Pressurized Water Reactor Using the RISMC Toolkit

In the Risk-Informed Safety Margin Characterization (RISMC) approach we want to understand not just the frequency of an event like core damage, but how close we are (or are not) to key safety-related events and how might we increase our safety margins. The RISMC Pathway uses the probabilistic margin approach to quantify impacts to reliability and safety by coupling both probabilistic (via stoch...

National Report on „Stress Tests“ NPP Dukovany and NPP Temelín Czech Republic Evaluation of Safety and Safety Margins in the light of the accident of the NPP Fukushima

Upgrade of the Monte Carlo code FIDO

During rf heating on minority ions and current drive the velocity distribution is determined by the balance between the wave-particle interaction and the relaxation through Coulomb collision. This is simulated by the Monte Carlo code fido [1–3], which solves the Fokker-Planck equation in the low collisionality banana-transport regime, including finite orbit width and rf induced transport. The f...