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    NEA Document
    OECD-NEA Piping Failure Data Exchange Project (OECD-NEA OPDE) Final Report
    NEA/CSNI/R(2012)16

    Several OECD member countries agreed to establish the OECD/NEA Piping Failure Data Exchange Project (OECD/NEA OPDE) to encourage multilateral co-operation in the collection and analysis of data relat...

    English Nuclear safety research Databases CSNI Safety of components and structures …
    Published date: 26 November 2012
    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
    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
    Joint project
    Studsvik Cladding Integrity Project (SCIP)

    On this page

    • SCIP phases
      • First phase (2004-2009)
      • Second phase (2009-2014)
      • Third phase (2014-2019)
      • Fourth phase (2019-2024)
        • Related external link

    SCIP phases

    First phase (2004-2009)

    Phase on...

    Fuel in nuclear safety Risk assessment Accident analysis and management Fuel cycle facility safety Nuclear safety research CSNI Safety Safety of components and structures Safety research …
    Published date: 14 April 2020
    Joint project
    Halden Reactor 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: 6 April 2020
    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
    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: 30 September 2020
    Publications and Reports
    Pressurised Water Reactor Main Steam Line Break (MSLB) Benchmark - Volume III

    This benchmark is based on a well-defined problem concerning a pressurised water reactor (PWR) main steam line break, which may occur as a consequence of the rupture of one steam line upstream of the...

    English Modelling and simulation Nuclear science Thermal hydraulics Verification and validation Nuclear safety research Uncertainty analysis Safety of components and structures Benchmark Thermal hydraulics and mechanics Pressurised water reactors …
    Published date: 22 November 2002
    Publications and Reports
    Pressurised Water Reactor Main Steam Line Break (MSLB) Benchmark - Volume II

    The benchmark is based on a well-defined problem concerning a PWR main steam line break, which may occur as a consequence of the rupture of one steam line upstream of the main steam isolation valves....

    English Modelling and simulation Nuclear science Thermal hydraulics Verification and validation Nuclear safety research Uncertainty analysis Safety of components and structures Benchmark Thermal hydraulics and mechanics Pressurised water reactors …
    Published date: 22 December 2000
    Publications and Reports
    Pressurised Water Reactor Main Steam Line Break (MSLB) Benchmark - Volume I

    Since the beginning of benchmark activities, two benchmark workshops took place. The first was held in Madrid, Spain (June 1998), and the second in Garching near Munich, Germany (March 1999). It was ...

    English Modelling and simulation Nuclear science Thermal hydraulics Verification and validation Nuclear safety research Uncertainty analysis Safety of components and structures Benchmark Thermal hydraulics and mechanics Pressurised water reactors …
    Published date: 1 January 1999
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