Search within our projects by using the filters below.

To access finished projects please click here.


ADVISE aims to advance the ultrasonic inspection of complex structured materials, for which conventional ultrasonic techniques suffer from severe performance limitations due to the micro and/or macro-structure.


The main objective and mission of the ATLAS+ project is to develop advanced structural assessment tools to address the remaining technology gaps for the safe and long term operation of nuclear reactor pressure coolant boundary systems.


Based on recent theoretical progresses and outcomes of recent European projects (e.g. FP7 SYNER-G, FP7 MATRIX, FP7 ASAMPSA_E), the NARSIS project aims at proposing some elements of improvement to be integrated in the current Probabilistic Safety Assessment (PSA) procedures.


The objective of NOMAD is the development, demonstration and validation of a nondestructive evaluation (NDE) tool for the local and volumetric characterisation of the embrittlement in operational reactor pressure vessels (RPVs).


The goal of the MEACTOS project is to improve the safety and reliability of Generation II and III nuclear power plants (NPPs) by improving the resistance of critical locations, including welds, to environmentally-assisted cracking (EAC) through the application of optimised surface machining and improved surface treatments.


The main objective of IL TROVATORE is to identify the best candidate ATF cladding materials for use in Gen-II and Gen-III/III+ LWRs and to validate them in an industrially-relevant environment, i.e. under neutron irradiation in PWR-like water.


The CORTEX project aims at developing core monitoring techniques that allow detecting, characterising and backtracking anomalies in nuclear reactors, before they can have any adverse effects on plant safety and availability.


The main objective of ASCOM is to help amplify and accelerate the ongoing process of making the IRSN ASTEC code a fully reliable tool for SA analyses and accident management by strengthening the activities of this ASTEC community in a consistent way.


The overall objective of the Management and Uncertainties of Severe Accident (MUSA) project is to assess the capability of SA codes when modelling reactor and SFP (Spent Fuel Pool) accident scenarios of Gen II and III.