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    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
    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
    Joint project
    Sandia Lower Head Failure Project

    During a severe accident, the lower head of a reactor pressure vessel (RPV) can be subjected to significant thermal and pressure loads. The lower head has the potential to fail, releasing large amoun...

    Risk assessment Accident analysis and management Nuclear safety research Joint project Safety of components and structures …
    Published date: 21 April 2020
    Joint project
    Steam Explosion Resolution for Nuclear Applications (SERENA) Project

    The Committee on the Safety of Nuclear Installations (CSNI) Working Group on Analysis and Management of Accidents (WGAMA) initiated a co-ordinated programme on Steam Explosion Resolution for Nuclear ...

    Risk assessment Accident analysis and management Information, data and knowledge management Nuclear safety research Ancillary data Safety of components and structures …
    Published date: 20 April 2020
    Joint project
    Three Mile Island Reactor Pressure Vessel Investigation Project (TMI-VIP)

    On 28 March 1979, a partial meltdown of the Three Mile Island unit 2 (TMI-2) reactor occurred at the TMI nuclear power plant near Harrisburg, Pennsylvania, United States.

    A TMI accident evaluation pr...

    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
    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
    Stress Corrosion Cracking and Cable Ageing Project (SCAP)

    The Stress Corrosion Cracking and Cable Ageing Project (SCAP) lasted four years (2006-2010). The project’s main objectives were to:

    • establish two complete databases with regard to major ageing pheno...
    Joint project
    Published date: 17 April 2020
    Joint project
    Cable Ageing Data and Knowledge (CADAK) Project

    In 2006, two subjects, stress corrosion cracking and the degradation of cable insulation were selected as the focus of the Stress Corrosion Cracking and Cable Ageing Project (SCAP). The project ran f...

    Nuclear safety research Joint project Safety of components and structures
    Published date: 17 April 2020
    Joint project
    SESAR Thermal-Hydraulics (SETH) Project

    The SESAR Thermal-hydraulics (SETH) Project began in 2001 and consisted of thermal-hydraulic experiments in support of accident management, which were carried out at facilities identified by the Comm...

    Thermal hydraulics
    Published date: 16 April 2020
    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)

    The TCOFF project provides a framework for the exchange of technical information on topics related to thermodynamic databases available for modelling the fuel/core degradation process, which include ...

    Fuel in nuclear safety Fuel studies Nuclear science Fission products Fukushima Accident analysis and management Fuel cycle facility safety Nuclear data Nuclear safety research Ancillary data Safety research Thermodynamics Thermodynamic data Fuel cycle physics and chemistry Accident management …
    Published date: 16 April 2020
    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
    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
    Source Term Evaluation and Mitigation (STEM) Project

    On this page

    • STEM phases
      • First phase (2011-2015)
      • Second phase (2016-2019)

    STEM phases

    First phase (2011-2015)

    The STEM Project was initiated with a first phase in 2011 to improve the general ...

    Fuel in nuclear safety Risk assessment Accident analysis and management Nuclear safety research CSNI Safety Safety research …
    Published date: 8 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
    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
    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
    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
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