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    Joint project
    International Common-cause Failure Data Exchange (ICDE) Project

    Common-cause failure (CCF) events can significantly affect the availability of nuclear power plant safety systems. In recognition of this, CCF data is systematically collected and analysed in several...

    Accident analysis and management Fuel cycle facility safety Safety of electrical systems Nuclear safety research Ancillary data CSNI Safety Safety of components and structures Safety research Risk assessment …
    Published date: 7 April 2020
    Joint project
    Loss of Forced Coolant (LOFC) Project

    The Committee on the Safety of Nuclear Installations (CSNI) Task Group on Advanced Reactor Experimental Facilities (TAREF) was established in 2007 and issued a report on the experimental facilities f...

    Fuel in nuclear safety Experiments Accident analysis and management Nuclear safety research CSNI Safety Safety of components and structures Codes and programs Safety research Risk assessment Gas-cooled reactors Thermal hydraulics …
    Published date: 7 April 2020
    Joint project
    Loss-of-fluid Test (LOFT) Project

    The Loss-of-fluid Test (LOFT) Research Programme was originally set up by the US Nuclear Regulatory Commission. Part of the programme was later broadened into an international collaboration project u...

    Risk assessment Accident analysis and management Verification and validation Fuel cycle facility safety Validation Nuclear safety research Safety of components and structures Codes and programs Safety research …
    Published date: 22 April 2020
    Joint project
    Material Scaling (MASCA) Project

    The Material Scaling (MASCA) Project was a follow-up of the RASPLAV Project and investigated in-vessel phenomena during a severe accident. Specifically, it addressed the influence of the chemical c...

    Risk assessment Accident analysis and management Nuclear safety research Joint project Safety of components and structures …
    Published date: 22 April 2020
    Joint project
    Melt Coolability and Concrete Interaction (MCCI) Project

    In a core melt accident, if the molten core is not retained in-vessel despite severe accident mitigation actions, the core debris will relocate to the reactor cavity region and interact with the stru...

    Risk assessment Light water reactors Accident analysis and management Fuel cycle facility safety Nuclear safety research Joint project Safety of components and structures Safety research …
    Published date: 22 April 2020
    Joint project
    NEST Hydrogen Containment Experiments for Reactor Safety (HYMERES) Project

    NEST HYMERES (Hydrogen containment experiments for reactor safety) project is addressing safety relevant phenomena in containments during accidents. It offers hands-on training opportunity during the...

    Nuclear Education, Skills and Technology (NEST) Framework Reactor design
    Published date: 6 December 2019
    Joint project
    NEST project dedicated to advanced remote technology and robotics for decommissioning

    This NEST project led by JAEA/CLADS will be dedicated to advanced remote technology for decommissioning under intense gamma-ray radiation environments (e.g robotics, virtual reality).

    A short program...

    Decommissioning Nuclear Education, Skills and Technology (NEST) Framework Remote and robotic system
    Published date: 18 February 2020
    Joint project
    NEST Small Modular Reactors (SMRs)

    This NEST project aims to integrate SMR research projects from the individual Participating Organisation countries into a broader and more impactful programme. It will include elements of technology ...

    Reactor physics Nuclear Education, Skills and Technology (NEST) Framework Spent fuel Reactor design
    Published date: 18 February 2020
    Joint project
    OECD-IAEA Paks Fuel Project

    During a fuel crud removal operation on the Paks-2 unit on 10 April 2003, several fuel assemblies were severely damaged. The assemblies were being cleaned in a special tank of the Paks Nuclear Power ...

    Fuel in nuclear safety Risk assessment Accident analysis and management Fuel cycle facility safety Nuclear safety research Safety of components and structures …
    Published date: 20 April 2020
    Joint project
    Piping Failure Data Exchange (OPDE) Project

    The goals of the Piping Failure Data Exchange (OPDE) Project were to:

    • collect and analyse piping failure event data to promote a better understanding of underlying causes, impact on operations and s...
    Nuclear safety research Joint project Safety of components and structures
    Published date: 17 April 2020
    Joint project
    Plant Safety Monitoring and Assessment System (PLASMA) Project

    Under an agreement with the Japan Atomic Energy Research Institute, (JAERI), the NEA supported an international research project with the goal of developing a plant safety monitoring and assessment s...

    Risk assessment Accident analysis and management Nuclear safety research Joint project Accident management Pressurised water reactors Safety research …
    Published date: 22 April 2020
    Joint project
    Preparatory Study on Analysis of Fuel Debris (PreADES) Project

    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 ...

    Fuel in nuclear safety Risk assessment Fukushima Accident analysis and management Fuel cycle facility safety Nuclear safety research CSNI Safety Safety research …
    Published date: 22 June 2022
    Joint project
    Primary Coolant Loop Test Facility (PKL) Project

    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...

    Finland WGAMA Accident analysis and management Thermal hydraulics Hungary Nuclear safety research Germany Accident management …
    Published date: 11 June 2021
    Joint project
    PSB-VVER Project

    The PSB-VVER is a large-scale thermal-hydraulics testing facility operated by the Electrogorsk Research and Engineering Centre (EREC) in Russia. The PSB-VVER Project was intended to provide the exper...

    Risk assessment Accident analysis and management Thermal hydraulics Nuclear safety research CSNI Joint project Safety of components and structures Codes and programs Pressurised water reactors Safety research …
    Published date: 22 April 2020
    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: 1 April 2022
    Joint project
    RASPLAV Project

    The RASPLAV* Project was regarded as a successor to the Three Mile Island Vessel Investigation Project (TMI-VIP) completed in 1993. The TMI-VIP Project was set up to examine and assess the conditio...

    Risk assessment Accident analysis and management Nuclear safety research CSNI Joint project Safety of components and structures …
    Published date: 22 April 2020
    Joint project
    Reduction of Severe Accident Uncertainties (ROSAU) Project

    The goal of the Reduction of Severe Accident Uncertainties (ROSAU) Project is to reduce knowledge gaps and uncertainties associated with severe accident progression by performing large-scale tests in...

    Risk assessment Accident analysis and management Fuel cycle facility safety Nuclear safety research CSNI Safety Safety of components and structures Safety research …
    Published date: 8 April 2020
    Joint project
    Rig-of-safety Assessment (ROSA) Project

    The Rig-of-safety Assessment (ROSA) Project aimed to resolve issues in thermal-hydraulics analyses relevant to light water reactor (LWR) safety using the Japanese rig-of-safety assessment/large-scale...

    Risk assessment Accident analysis and management Thermal hydraulics Fuel cycle facility safety Nuclear safety research CSNI Safety Safety research …
    Published date: 8 April 2020
    Joint project
    Rod Bundle Heat transfer (RBHT) Project

    The goal of the Rod Bundle Heat transfer (RBHT) Project is to conduct experiments in the RBHT facility in the United States in order to:

    • simulate reflood scenarios in a prototypical PWR rod bundle s...
    Fuel in nuclear safety Risk assessment Accident analysis and management Thermal hydraulics Nuclear safety research CSNI Safety Safety of components and structures Safety research …
    Published date: 8 April 2020
    Joint project
    Sandia Fuel Project (SFP)

    The goal of the project was to provide experimental data relevant for hydraulic and ignition phenomena of prototypic water reactor fuel assemblies. The intended scope of work was defined in an expert...

    Fuel in nuclear safety Risk assessment Accident analysis and management Fuel cycle facility safety Nuclear safety research Joint project Safety of components and structures …
    Published date: 21 April 2020
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