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    Lead-cooled Fast Reactor Benchmark (LFR)

    Lead-cooled Fast Reactors (LFR) are rather new concepts which have gathered increasing international attention after the Generation-IV International Forum (GIF) selected them as promising candidates ...

    Generation IV reactors Verification and validation Verification Validation Liquid metal reactors Benchmark Reactor physics …
    Published date: 31 January 2023
    Activity
    Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS)

    The Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS) studies the reactor physics, fuel performance, and radiation transport and shielding in present and future nu...

    Nuclear fuel Reactor physics Multi-physics simulations Fuel studies Light water reactors Thermal hydraulics WPRS Pressurised heavy water reactors Reactor physics Multiphysics …
    Published date: 24 January 2023
    Activity
    Pressurised Water Reactor MOX/UO2 Core Transient Benchmark

    PWR MOX/UO2 Core Transient Benchmark

    Verification Benchmark Reactor physics
    Published date: 7 December 2022
    Activity
    MeshTal Viewer user manual

    MeshTal Viewer user manual

    Nuclear science
    Published date: 25 November 2022
    Activity
    JANIS

    JANIS (Java-based nuclear information software) is an application designed to facilitate the visualisation and manipulation of nuclear data. JANIS will be helpful to engineers and physicists who use ...

    Nuclear data Databases
    Published date: 24 November 2022
    Activity
    WPFC Expert Group on Reactor Coolants/Components Technology (EGCoCoT)

    Under the guidance of the Working Party on Scientific Issues of Advanced Fuel Cycles (WPFC), the Expert Group on Reactor Coolants and Components Technology (EGCoCoT) undertakes activities with the go...

    Nuclear fuel WPFC EGLM Fuel studies NSC Nuclear science EGCoCoT Liquid metal reactors Partitioning and transmutation Fuel cycle physics and chemistry …
    Published date: 21 November 2022
    Activity
    IRPhE Technical Review Group

    The International Reactor Physics Experiment Evaluation (IRPhE) Technical Review Group provides the nuclear community with qualified benchmark data sets by collecting reactor physics experimental dat...

    Modelling and simulation Reactor physics Verification and validation Verification Validation Benchmark Reactor physics …
    Published date: 10 November 2022
    Activity
    International Criticality Safety Benchmark Evaluation Project (ICSBEP) Handbook

    The International Criticality Safety Benchmark Evaluation Project (ICSBEP) Handbook contains criticality safety benchmark specifications that have been derived from experiments that were performed at...

    Modelling and simulation Criticality safety Verification and validation Verification Benchmark …
    Published date: 10 November 2022
    Activity
    International Criticality Safety Benchmark Evaluation Project (ICSBEP)

    The primary purpose of the International Criticality Safety Benchmark Evaluation Project (ICSBEP) is to compile critical and subcritical benchmark experiment data into a standardised format that allo...

    Criticality safety Nuclear science Criticality WPNCS ICSBEP …
    Published date: 10 November 2022
    Activity
    FIDES-II Cross-Cutting Pillars

    The FIDES-II framework is designed to do more than just produce data on transient fuel behavior and safety related issues. 

    Fuel in nuclear safety Nuclear science Nuclear safety research Reactor fuel performance
    Published date: 10 November 2022
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