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    NEA Document
    SOCRAT (Seismic Simulation of Overhead Crane on Shaking Table) International Benchmark Final Report
    NEA/CSNI/R(2023)11

    Background
    Bridge cranes, which are components that handle devices designed to lift and transfer heavy loads, are widely used in the nuclear sector. Assessing the dynamic behaviour of bridge cranes is...

    Nuclear safety Nuclear safety research CSNI PRG CSNI Safety Benchmark Safety research …
    Published date: 19 March 2025
    NEA Document
    Best Practice Guidelines for the Use of CFD in Nuclear Reactor Safety Applications – 2024 Update
    NEA/CSNI/R(2022)10

    The aim of this second revision of the Best Practice Guidelines (BPG) is to provide guidance to the user of computational fluid dynamics (CFD) codes, both novice and experienced, in the field of nucl...

    Nuclear safety Nuclear safety research CSNI PRG CSNI Safety Safety of components and structures Reactor technology Safety research CFD Best practices …
    Published date: 19 March 2025
    NEA Document
    NEA Kappa Workshop on Earthquake Ground Motions on Rock Sites 25-28 May 2021
    NEA/CSNI/R(2023)10

    The objective of this “Kappa Workshop on Earthquake Ground Motions on Rock Sites” (held remotely from 25-28 May 2021), organised by the NEA Working Group on Integrity and Ageing of Components and Str...

    WGIAGE Nuclear safety Nuclear safety research CSNI PRG CSNI …
    Published date: 17 March 2025
    Activity
    NEA News

    NEA News is the professional journal of the Nuclear Energy Agency (NEA). It features articles on the latest issues concerning the economic and technical aspects of nuclear energy, nuclear safety and ...

    Nuclear law Human aspects of nuclear safety Radiological protection Nuclear science Nuclear economics Nuclear technology Decommissioning and legacy management Radioactive waste management Nuclear safety research NEA News publication Nuclear energy and climate change Nuclear safety regulation …
    Published date: 25 February 2025
    Activity
    Working Group on Analysis and Management of Accidents (WGAMA)

    The Working Group on the Analysis and Management of Accidents (WGAMA) focuses on the NEA activities related to potential design-basis and beyond design-basis accidents in nuclear reactors and related...

    Risk assessment WGAMA Accident analysis and management Nuclear safety research CSNI Safety Accident management Risk …
    Published date: 4 February 2025
    Activity
    Nuclear Safety Research Joint Projects

    One of the major achievements of the OECD Nuclear Energy Agency (NEA) is the knowledge it has helped to generate through the organisation of joint international research projects. Such projects, prim...

    Nuclear safety Nuclear safety research Joint project
    Published date: 4 February 2025
    Joint project
    COPS The COrium Properties for reactor Simulation and uncertainties (COPS)

    Photo of CEA VITI facility

    The COrium Properties for reactor Simulation and uncertainties (COPS) project began in April 2024 its five-year programme to investigate the thermo-physical properties of c...

    Nuclear safety Nuclear safety research Accident management
    Published date: 4 February 2025
    Joint project
    THAI Experiments on Mitigation measures, and source term issues to support analysis and further Improvement of Severe accident management measures (THEMIS) Project

    Multi-compartment THAI+ test facility, Becker Technologies GmbH.

     

    In the wake of the NEA THAI project, conducted in three phases from 2007 until 2019, a new project, THAI Experiments on Mitigation m...

    Fission products Accident analysis and management Thermal hydraulics Hydrogen Nuclear safety research Joint project Accident management …
    Published date: 4 February 2025
    Joint project
    Primary Coolant Loop Test Facility (PKL) Project

    PKL facility. Photo: FRAMATOME, Germany

    The Primärkreislauf-Versuchsanlage (Primary Coolant Loop Test Facility [PKL]) is a facility owned and operated by Framatome GmbH (formerly AREVA NP) in Erlange...

    Accident analysis and management Thermal hydraulics Nuclear safety research Accident management
    Published date: 4 February 2025
    Joint project
    Reduction of Severe Accident Uncertainties (ROSAU) Project

    Left: Test facility for qualification of melt spreading tests. Photo: Argonne National Laboratory (ANL).
    Right: Example of corium melt pouring for a melt spreading preparatory test. Photo: Argonne Nat
    ...

    Accident analysis and management Nuclear safety research CSNI Safety Safety research …
    Published date: 4 February 2025
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