This document proposes the creation of an expert group on the integrated management of accident-oriented radioactive waste, which would produce valuable insights on the management of accident-oriente...

NEA and NRA held joint conference on regulators' views in Tokyo, Japan 10 years after TEPCO Fukushima Daiichi NPS Accident. 

When looking for a validation experiment for CFD application to reactor simulation for either design or safety studies, it appears that available data often suffer from a lack of local measurements, ...

Scheme of the ROSA LSTF facility, JAEA

The Rig-of-safety Assessment (ROSA) Project aimed to resolve issues in thermal-hydraulics analyses relevant to light water reactor (LWR) safety using the Japa...

Photo: RBHT Test Facility. US NRC.

Modelling reactor core behaviour under accident conditions with delayed re-introduction of cooling water (commonly referred to as reflood) is a challenge for safety...

In the current project, a new systematic approach has been developed, called SAPIUM (systematic approach for input uncertainty quantification methodology) for transparent and rigorous model IUQ. This...

Lyon, France, 8-10 September 1997

Scheme of the PKL facility, Framatome GmbH.

The SESAR Thermal-hydraulics (SETH) Project began in 2001 and consisted of thermal-hydraulic experiments in support of accident management, which were ca...

Specialist Workshop on Advanced Measurement Method and Instrumentation for Enhancing Severe Accident Management in a Nuclear Power Plant

Passive thermal-hydraulic systems are widely used in nuclear reactor safety and design. For example, primary circuits in existing boiling and pressurised water reactors are designed to take advantage...