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    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 institution...

    Fuel in nuclear safety Nuclear fuel Nuclear science FIDES Nuclear safety research Accident tolerant fuels Reactor fuel performance …
    Published date: 14 March 2023
    Joint project
    Thermodynamics of Advanced Fuels – International Database (TAF-ID) public version

    The TAF-ID public version contains only data already published in open literature. Currently, the following systems are available in the public version:

    • oxide-carbide fuel (U-Pu-O-C, released Decemb...
    Material science Fuel studies Nuclear science Materials science Thermodynamics Thermodynamic data Databases TAF-ID Codes and programs …
    Published date: 23 February 2023
    Joint project
    Thermodynamics of Advanced Fuels - International Database (TAF-ID)

    On this page

    • Why is thermodynamic data for analyses involving nuclear fuel needed?
    • How is thermodynamic data calculated?
    • Available tools for thermodynamic calculations
    • Project organisation
    • TAF-ID i...
    Material science Structural materials Fuel studies Nuclear science Materials science Thermodynamic data TAF-ID …
    Published date: 23 February 2023
    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: 17 January 2023
    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: 20 December 2022
    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 Accident management
    Published date: 13 December 2022
    Joint project
    Experimental Thermal Hydraulics for Analysis, Research and Innovations in NUclear Safety (ETHARINUS) Project

    PKL facility. Photo: FRAMATOME, Germany

    The Experimental Thermal Hydraulics for Analysis, Research and Innovations in Nuclear Safety (ETHARINUS) project serves the objectives of investigating phenome...

    Accident analysis and management Thermal hydraulics Nuclear safety research Accident management
    Published date: 9 December 2022
    Joint project
    Sandia Fuel Project (SFP)

    Photos: SFP testing. Left: fuel assembly after a Zr fire; right: fire ignition test. SNL/USNRC.

    The goal of the Sandia Fuel Project was to provide experimental data relevant for hydraulic and ignitio...

    Fuel in nuclear safety Nuclear fuel Accident analysis and management Fuel cycle facility safety Nuclear safety research Joint project …
    Published date: 9 December 2022
    Joint project
    Thermodynamic Characterisation of Fuel Debris and Fission Products Based on Scenario Analysis of Severe Accident Progression at Fukushima Daiichi Nuclear Power Station (TCOFF)

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

    TCOFF Phases

    First Phase (2017-2020)

    The TCOFF project established a framework for the exchange of technical...

    Nuclear science Fission products Fukushima Thermodynamic data Nuclear safety research Safety research …
    Published date: 7 December 2022
    Joint project
    Studsvik Cladding Integrity Project (SCIP)

    Left: Scheme of Studsvik LOCA test facility Right: Microstructure of fragmented nuclear fuel, Studsvik

    On this page

    • SCIP phases
      • First phase (2004-2009)
      • Second phase (2009-2014)
      • Third phase (2014-2...
    Fuel in nuclear safety Nuclear fuel Fuel cycle facility safety Nuclear safety research CSNI Back-end …
    Published date: 7 December 2022
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