After the Fukushima accident, the interest on hydrogen combustion hazard management has
increased considerably. Many European nuclear plants reinforced their strategies for severe …

Abstract The evaluation of Passive Autocatalytic Recombiners (PARs) performance has
been foreseen from the EU stress tests in the framework of a complementary and …

The confinement of radioactive material in a nuclear power plant, including the discharge
control and the release minimization, is a fundamental safety function to be ensured in a …

Abstract The Stress Tests accomplished by the European nuclear plants assume to be a
complementary and comprehensive review of the safety of nuclear facilities, taking into …

Containment safety analyses of Design Basis Accidents (DBAs) rely on the use of Lumped
Parameters (LP) codes, and therefore, on pressure and temperature averaged values. In …

AP1000® is a Generation III+ reactor in which all safety systems relay on passive elements.
AP1000 containment includes an In-containment Refueling Water Storage Tank (IRWST), a …

This document explores the role of CFD in nuclear safety studies, with a particular focus on
advancements in Spain and Portugal. The field of nuclear safety has increasingly included …

Historically, the deterministic safety analysis simulations for large dry containments of
operating nuclear power plants have been done with nuclear legacy codes using the …

Severe accidents research activities in Spain have grown substantially since the Fukushima-
Daiichi accident. Most of these research activities have been conducting by a few …

Both units of the Chinshan plant have been approved for decommissioning. However, fuel
assemblies cannot be discharged from the reactor core because the spent fuel pool (SFP) is …