Image: QUENCH facility at KIT. Court. KIT. 

The purpose of the QUENCH-ATF project is to investigate the chemical, mechanical and thermal-hydraulics behaviour of ATF claddings in Design Basis Accident...

This report provides descriptions of the current status of PSA programmes in member countries; including basic background information, guidelines, various PSA applications, major results in recent st...

Aix-en-Provence, 7-9 November 2005

Uncertainty in relation to several severe accident phenomena plays a major role in probabilistic safety analyses involving beyond-design-basis accident scenarios fo...

The Preparatory Study on Analysis of Fuel Debris (PreADES) project and the Analysis of information from Reactor buildings and Containment vessels of Fukushima Daiichi Nuclear Power Station (ARC-F) pr...

The OECD Nuclear Energy Agency (NEA) in collaboration with the Canadian Nuclear Safety Commission (CNSC) hosted an international, multi-sector workshop on 14-18 December 2020 on safely regulating inn...

This benchmark incorporated full 3-D modelling of the reactor core into system transient codes for best-estimate simulations of the interactions between reactor core behaviour and plant dynamics and ...

This benchmark is based on a well-defined problem concerning a pressurised water reactor (PWR) main steam line break, which may occur as a consequence of the rupture of one steam line upstream of the...

The benchmark is based on a well-defined problem concerning a PWR main steam line break, which may occur as a consequence of the rupture of one steam line upstream of the main steam isolation valves....

Since the beginning of benchmark activities, two benchmark workshops took place. The first was held in Madrid, Spain (June 1998), and the second in Garching near Munich, Germany (March 1999). It was ...

This benchmark is based on a well-defined problem concerning a pressurised water reactor (PWR) main steam line break, which may occur as a consequence of the rupture of one steam line upstream of the...