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    Activity
    Thermal hydraulic code validation benchmark for high temperature gas-cooled reactors using HTTF data (HTGR T/H)

    High-temperature gas-cooled nuclear reactors are one of the next generation reactor designs. This benchmark consists of a multi-staged code-to-code-to-data thermal hydraulics code validation benchmar...

    Thermal hydraulics Verification and validation Verification Validation Benchmark Reactor physics …
    Published date: 19 July 2023
    Activity
    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: 9 June 2023
    Event
    International workshop on thermal hydraulic code validation benchmark for high temperature gas-cooled reactors using HTTF data (HTGR T/H)
    5 - 6 June 2023
    Oregon State University, Corvallis, Oregon, United States

    The NEA thermal hydraulic code validation benchmark for high temperature gas-cooled reactors using HTTF data (HTGR T/H), supervised by the Expert Group on Reactor Core Thermal-Hydraulics and Mechanic...

    Nuclear science Thermal hydraulics and mechanics Reactor physics Reactor physics NSC Thermal hydraulics Verification and validation Verification Validation Benchmark …
    Published date: 20 April 2023
    Activity
    Subgroup on Uncertainty Analysis in Modelling (UAM) for Design, Operation and Safety Analysis of Sodium-cooled Fast Reactors (SFR-UAM)

    The Subgroup on Uncertainty Analysis in Modelling (UAM) for Design, Operation and Safety Analysis of Sodium-cooled Fast Reactors (SFR-UAM) was formed to check the use of best-estimate codes and data....

    Sodium-cooled reactor Verification Fast reactor Benchmark Reactor physics …
    Published date: 24 May 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
    News
    New edition: the International Handbook of Evaluated Criticality Safety Benchmark Experiments

    The 2021 edition can be downloaded online.

    Modelling and simulation Criticality safety Criticality Verification and validation Verification Validation ICSBEP Benchmark …
    Published date: 22 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 Handbook of Evaluated Reactor Physics Benchmark Experiments (IRPhE)

    The International Handbook of Evaluated Reactor Physics Benchmark Experiments (IRPhE) contains reactor physics benchmark specifications that have been derived from experiments that were performed at ...

    Modelling and simulation Reactor physics Verification and validation Verification Validation Benchmark Reactor physics …
    Published date: 9 November 2022
    Activity
    Forsmark 1 and 2 Boiling Water Reactor Stability Benchmark

    Forsmark 1 and 2 Boiling Water Reactor Stability Benchmark

    Verification and validation Verification Reactor physics
    Published date: 2 August 2022
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