External or internal hazards, combined with multiple failures of components and safety
systems or human errors can lead to a reactor core melt. In that case the reactor pressure …

In the field of research for Severe Accidents in Nuclear Reactors, and more specifically In-
Vessel Corium Retention, prediction of transient heat loads on the vessel wall is necessary …

The present work addresses the question of corium–ceramic interaction in a core catcher
during a core-melt accident in a nuclear power plant. It provides an original insight into …

The paper is devoted to the presentation of validation cases carried out for the models
describing the corium behaviour in the “lower plenum” of the reactor vessel implemented in …

D thermohydraulic CFD code CONV was applied to the simulation of FSt4 LIVE water test.
Two calculations were performed: in the first one the homogeneous heating of liquid was …

Thermohydraulic CFD code CONV was applied to the simulation of L-4 LIVE test with
simulant melt 80 mole% KNO3–20 mole% NaNO3 as working liquid. Two calculations were …

From the very beginning of nuclear era the mission of fast neutron reactors has been
conceived in a double functionality as a source of energy and, at the same time, of artificial …

[en] Core debris retention in the reactor vessel (in-vessel retention) is an important area of
research in the field of nuclear power reactor severe accident analysis. The understanding …