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    Joint project
    Thermodynamic Characterisation of Fuel Debris and Fission Products Based on Scenario Analysis of Severe Accident Progression (TCOFF)

    Image: Microscopic examination of U-bearing particles collected at Fukushima-Daiichi, JAEA

    TCOFF Phases

    First Phase (2017-2020)

    The Thermodynamic Characterisation of Fuel Debris and Fission Products ...

    Nuclear science Fission products Fukushima Thermodynamic data Nuclear safety research Safety research …
    Published date: 5 May 2025
    Joint project
    Experiments on Source Term for Delayed Releases (ESTER) Project

    CHIP experimental facility to study fission product transport and deposition in the primary circuit. Photo: ASNR

    Following several years of experimental research on source term analysis conducted und...

    Accident analysis and management Nuclear safety research CSNI Joint project Accident management …
    Published date: 24 April 2025
    Joint project
    International Common-cause Failure Data Exchange (ICDE) Project

    Scheme showing the technical scope of NEA ICDE project activities, NEA 

    Common-cause failure (CCF) events can significantly affect the availability of safety systems of nuclear power plants. In recog...

    Risk assessment Nuclear safety research CSNI Probabilistic risk assessment
    Published date: 4 April 2025
    Joint project
    QUENCH-ATF project

    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...

    Nuclear science Nuclear safety research Joint project Accident Tolerant Fuels Accident tolerant fuels …
    Published date: 2 April 2025
    Joint project
    Second Framework for Irradiation Experiments (FIDES‑II)

    The NEA Second Framework for Irradiation Experiments (FIDES-II) supports the fuel and material experimental needs of nuclear safety regulators, technical support organisations, research institutions ...

    Fuel in nuclear safety Nuclear fuel Nuclear science FIDES Nuclear safety research Accident tolerant fuels Reactor fuel performance …
    Published date: 2 April 2025
    Joint project
    COPS The COrium Properties for reactor Simulation and uncertainties (COPS)

    Photo of CEA VITI facility

    The COrium Properties for reactor Simulation and uncertainties (COPS) project began in April 2024 its five-year programme to investigate the thermo-physical properties of c...

    Nuclear safety Nuclear safety research Accident management
    Published date: 4 February 2025
    Joint project
    THAI Experiments on Mitigation measures, and source term issues to support analysis and further Improvement of Severe accident management measures (THEMIS) Project

    Multi-compartment THAI+ test facility, Becker Technologies GmbH.

     

    In the wake of the NEA THAI project, conducted in three phases from 2007 until 2019, a new project, THAI Experiments on Mitigation m...

    Fission products Accident analysis and management Thermal hydraulics Hydrogen Nuclear safety research Joint project Accident management …
    Published date: 4 February 2025
    Joint project
    Primary Coolant Loop Test Facility (PKL) Project

    PKL facility. Photo: FRAMATOME, Germany

    The Primärkreislauf-Versuchsanlage (Primary Coolant Loop Test Facility [PKL]) is a facility owned and operated by Framatome GmbH (formerly AREVA NP) in Erlange...

    Accident analysis and management Thermal hydraulics Nuclear safety research Accident management
    Published date: 4 February 2025
    Joint project
    Reduction of Severe Accident Uncertainties (ROSAU) Project

    Left: Test facility for qualification of melt spreading tests. Photo: Argonne National Laboratory (ANL).
    Right: Example of corium melt pouring for a melt spreading preparatory test. Photo: Argonne Nat
    ...

    Accident analysis and management Nuclear safety research CSNI Safety Safety research …
    Published date: 4 February 2025
    Joint project
    Rod Bundle Heat Transfer (RBHT) Project

    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...

    Accident analysis and management Thermal hydraulics Nuclear safety research Joint project Accident management …
    Published date: 4 February 2025
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