The Component Operational Experience, Degradation and Ageing Programme (CODAP) combines the follow-up of two previous NEA projects: the Pipe Failure Data Exchange Project (OPDE) and the stress corros...

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...

The experimental investigations carried out in the frame of the THAI (2007-2009) and THAI-2 (2011-2014) projects contributed significantly to improve the understanding of hydrogen and fission-product...

^{View of the ATLAS experimental loop. KAERI, Korea}

The Advanced Thermal-hydraulic Test Loop for Accident Simulation (ATLAS) Project was referenced in The Fukushima Daiichi Nuclear Power Plant Accident...

The Halden Reactor Project has been in operation since 1958 and is the oldest NEA joint project. It brings together an important international technical network in the area of nuclear safety ranging ...

The Experimental Thermal Hydraulics for Analysis, Research and Innovations in Nuclear Safety (ETHARINUS) project serves the objectives of investigating phenomena where the knowledge base for safety a...

The Primärkreislauf-Versuchsanlage (Primary Coolant Loop Test Facility [PKL]) is a facility owned and operated by Framatome GmbH (formerly AREVA NP) in Erlangen, Germany, to perform experiments on th...

In the wake of the THAI project, conducted in three phases from 2007 until 2019, a new project, "THAI Experiments on Mitigation measures, and source term issues to support analysis and further Improv...

Following several years of experimental research in the field of source terms analysis in the BIP, STEM and THAI joint projects but also other activities, the NEA Working Group on the Analysis and Ma...

The Preparatory Study on Analysis of Fuel Debris (PreADES) project was proposed as a near-term project by the Senior Expert Group on Safety Research Opportunities Post-Fukushima (SAREF).

PreADES was ...