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    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
    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 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
    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
    Event
    Multi-sector workshop on innovative regulation: Challenges and benefits of harmonising the licensing process for emerging technologies
    14 - 18 December 2020
    Zoom webinar

    The OECD Nuclear Energy Agency (NEA) in collaboration with the Canadian Nuclear Safety Commission (CNSC) hosted an international, multi-sector workshop on 14-18 December 2020 on safely regulating inn...

    Nuclear innovation Nuclear safety research Innovation Nuclear safety regulation
    Published date: 5 January 2021
    NEA Document
    Proceedings of the Workshop on Evaluation of Uncertainties in Relation to Severe Accidents and Level-2 Probabilistic Safety Analysis
    NEA/CSNI/R(2007)2

    Aix-en-Provence, 7-9 November 2005

    Uncertainty in relation to several severe accident phenomena plays a major role in probabilistic safety analyses involving beyond-design-basis accident scenarios fo...

    English Risk assessment Accident analysis and management Uncertainty quantification Nuclear safety research Uncertainty analysis CSNI …
    Published date: 26 February 2007
    NEA Document
    Use and Development of Probabilistic Safety Assessments at Nuclear Facilities
    NEA/CSNI/R(2019)10

    This report provides descriptions of the current status of PSA programmes in member countries; including basic background information, guidelines, various PSA applications, major results in recent st...

    Fukushima WGRISK Nuclear safety Nuclear safety research CSNI Probabilistic risk assessment …
    Published date: 15 September 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 Accident Tolerant Fuels
    Published date: 24 August 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
    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
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