• About us
  • Topics
  • News and resources
  • Learning and tools
×
Home
About us
  • About us
  • Topics
  • Topics
  • News and resources
  • News and resources
  • Learning and tools
  • Learning and tools
  • Copyright © 2023 OECD. All rights reserved.
    DATA BANK
    my nea
    1. Home
    2. Results page
    • Relevance
    • Date
    • Title
    Reset all
    Joint project
    Search
    57
    results
    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
    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
    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 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
    • Page 4/6
    • <<
    • <
    • 2
    • 3
    • 4
    • 5
    • 6
    • >
    • >>
    • 10 per page
      • 10 per page
      • 20 per page
      • 50 per page
      • All in one page
    Stay informed
    Receive monthly updates on NEA work, activities and newly released reports.
    SUBSCRIBE
    Follow us
    Follow the NEA on Twitter, LinkedIn, Facebook and YouTube.
    VACANCIES
    CONTACT AND PRACTICAL INFORMATION
    DATA BANK
    ACRONYMS
    ABOUT US
    History and statute
    Who we are
    What we do
    How we work
    Founding documents
    Privacy
    Terms
    TOPICS
    Nuclear safety research
    Nuclear safety regulation
    Human aspects of nuclear safety
    Radiological protection
    Radioactive waste management
    Decommissioning and legacy management
    Nuclear science
    Nuclear technology
    Nuclear economics
    Nuclear law
    NEWS AND RESOURCES
    News and events
    Publications and reports
    Projects
    Co-sponsored events
    LEARNING AND TOOLS
    Train with the NEA
    Databases, programs and tools
    Learn online
    NEA-SERVICED BODIES
    Generation IV International Forum (GIF)
    International Framework for Nuclear Energy Cooperation (IFNEC)
    Multinational Design Evaluation Programme (MDEP)
    Copyright © 2023 OECD. All rights reserved.
    Privacy
    Terms
    • en English
    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
    hpU9w62EUkvnv65m