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    Safety of components and structures
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    Joint project
    Component Operational Experience, Degradation and Ageing Programme (CODAP)

    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...

    Fuel in nuclear safety Risk assessment Accident analysis and management Nuclear safety research Databases CSNI Safety Safety of components and structures Safety research …
    Published date: 29 April 2022
    Joint project
    Halden Human Technology Organisation (HTO) Project

    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 ...

    Risk assessment Accident analysis and management Fuel cycle facility safety Nuclear safety research CSNI Safety Safety of components and structures Safety research …
    Published date: 10 November 2021
    News
    Long-term management and reliability of reactor core and containment cooling systems

    The NEA Working Group on Analysis and Management of Accidents (WGAMA) organised a specialist workshop entitled “Reactor core and containment cooling systems: Long-term management and reliability (RCC...

    News brief WGAMA Accident analysis and management Nuclear safety research Safety of components and structures Accident management …
    Published date: 29 October 2021
    Activity
    Pressurised Water Reactor Main Steam-Line Break (MSLB) Benchmark

    This benchmark incorporated full 3-D modelling of the reactor core into system transient codes for best-estimate simulations of the interactions between reactor core behaviour and plant dynamics and ...

    Modelling and simulation Thermal hydraulics Verification and validation Nuclear safety research Uncertainty analysis Safety of components and structures Benchmark Thermal hydraulics and mechanics …
    Published date: 26 July 2021
    Activity
    Working Group on Integrity and Ageing of Components and Structures (WGIAGE)

    The main mission of the Working Group on Integrity and Ageing of Components and Structures (WGIAGE) is to advance the current understanding of the relevant aspects related with ensuring the integrity...

    Structural materials WGIAGE Nuclear safety research Safety Safety of components and structures …
    Published date: 3 May 2021
    Activity
    Committee on the Safety of Nuclear Installations (CSNI)

    The Committee on the Safety of Nuclear Installations (CSNI) is responsible for NEA programmes and activities that support maintaining and advancing the scientific and technical knowledge base of the ...

    Fuel in nuclear safety Risk assessment Accident analysis and management Fuel cycle facility safety Safety of electrical systems External hazards and nuclear safety Nuclear safety research CSNI Safety Safety of components and structures …
    Published date: 10 February 2021
    Activity
    Senior Expert Group on Safety Research Opportunities Post-Fukushima (SAREF)

    The Senior Expert Group on Safety Research Opportunities Post-Fukushima (SAREF) was established at the June 2013 CSNI meeting to identify research activities to address safety research knowledge gaps...

    Fukushima Fuel cycle facility safety Nuclear safety research CSNI Safety Safety of components and structures …
    Published date: 4 February 2021
    News
    New Joint Project: Studsvik Material Integrity Life Extension (SMILE)

    New Joint Project: Studsvik Material Integrity Life Extension (SMILE)

    News brief Nuclear safety research Safety of components and structures Safety research
    Published date: 26 January 2021
    Activity
    Task Group on Advanced Reactor Experimental Facilities (TAREF)

    A Task Group on Advanced Reactor Experimental Facilities (TAREF) had been set up to provide an overview of facilities suitable for carrying out safety research on gas-cooled and sodium fast reactors....

    Fuel cycle facility safety Nuclear safety research CSNI Safety Safety of components and structures …
    Published date: 28 April 2020
    Activity
    Task Group on Sump Clogging

    The Task Group on Sump Clogging had been set up to update the State-of-the-art Report (SOAR) on Knowledge Base for Emergency Core Cooling System Recirculation Reliability issued in 1996, and with foc...

    Nuclear safety research CSNI Safety Safety of components and structures
    Published date: 28 April 2020
    Activity
    CSNI Action Plan in the Area of Safety Margins

    The CSNI Action Plan in the Area of Safety Margins was set up by the Committee on the Safety of Nuclear Installations (CSNI),

    Fuel cycle facility safety Nuclear safety research CSNI Safety Safety of components and structures Operating experience Nuclear safety regulation …
    Published date: 27 April 2020
    Activity
    Task Group on Safety Margin Applications and Assessment (SM2A)

    This task group was set up to carry out a pilot project using the methodology propsed in the final SMAP report published in 2007. In this pilot project, the SMAP methodology was applied to the Zion n...

    Accident analysis and management Nuclear safety research CSNI Safety Safety of components and structures …
    Published date: 27 April 2020
    Joint project
    Bubbler Condenser Project

    There are several VVER-440/213* type nuclear power plants operating in the Czech Republic, Hungary, Slovak Republic, Russia and Ukraine. VVER-440/213 pressurised water reactors (PWRs) have a pressure...

    Risk assessment Accident analysis and management Fuel cycle facility safety Nuclear safety research Joint project Safety of components and structures Accident management Pressurised water reactors Risk …
    Published date: 22 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
    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
    Activity
    Senior Expert Group on Safety Research / Support Facilities for Existing and Advanced Reactors 2 (SESAR/SFEAR2)

    The Senior Expert Group on Safety Research / Support Facilities for Existing and Advanced Reactors 2 (SESAR/SFEAR2) is responsible for reviewing and updating the previous SESAR assessments of researc...

    Fuel cycle facility safety Nuclear safety research CSNI Safety Safety of components and structures Safety research …
    Published date: 22 April 2020
    Activity
    Task Group on Robustness of Electrical Systems of NPPs (ROBELSYS)

    A Task Group on the Robustness of Electrical Systems of NPPs in Light of the Fukushima Daiichi Accident (ROBELSYS) had been set up to improve the understanding of nuclear power plant electrical syste...

    Electrical systems Safety of electrical systems Nuclear safety research CSNI Safety Safety of components and structures …
    Published date: 22 April 2020
    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
    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
    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
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