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    Activity
    SINBAD - Shielding Integral Benchmark Archive and Database

    https://www.oecd-nea.org/tools/ierequest/start/package/NEA-1939%2501The Shielding Integral Benchmark Archive and Database (SINBAD) database contains compilations for more than 100 reactor shielding, ...

    Transport Experiments Radiation Databases Radiation transport and shielding Reactor physics Integral experiments Verification and validation Validation SINBAD Benchmark …
    Published date: 14 April 2025
    News
    New release: The International Handbook of Evaluated Criticality Safety Benchmark Experiments

    NEA released the International Criticality Safety Benchmark Evaluation Project (ICSBEP) Handbook which contains criticality safety benchmark specifications

    Modelling and simulation Criticality safety Nuclear science Criticality Verification and validation Validation ICSBEP Benchmark …
    Published date: 21 November 2024
    NEA Working Paper
    Automated Conversion of International Criticality Safety Benchmark Models: Developing a Reproducible Serpent-2 Model Repository from MCNP Inputs
    NEA/WKP(2024)5

    The Serpent-2 software is a three-dimensional continuous-energy neutron and photon transport code, developed at the Technical Research Centre of Finland (VTT) (Leppänen, 2015), and is one of the most...

    WPEC Nuclear science Validation Nuclear data processing
    Published date: 7 November 2024
    NEA Working Paper
    Traditional and Novel Measurement Methods for Validation of Multi-Physics Modelling and Simulation Tools
    NEA/WKP(2023)3

    The NEA Nuclear Science Committee (NSC) mandated the Expert Group on Multi-Physics Experimental Data, Benchmarks and Validation (EGMPEBV) in 2014 to provide oversight of activities associated with th...

    Nuclear science WPRS Multiphysics Reactor fuel performance Multiphysics EGMUP Modelling and simulation Measurement NSC Verification and validation Validation Benchmark …
    Published date: 18 June 2024
    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: 14 June 2024
    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
    Benchmark for Uncertainty Analysis in Best-Estimate Modelling for Design, Operation and Safety Analysis of Light Water Reactors (LWR-UAM)

    The goal of the Benchmark for Uncertainty Analysis in Best-Estimate Modelling for Design, Operation and Safety Analysis of Light Water Reactors (LWR-UAM) is to determine the uncertainty in light wate...

    Modelling and simulation Reactor physics Light water reactors Verification and validation Validation Uncertainty quantification Uncertainty analysis Benchmark Reactor physics Pressurised water reactors …
    Published date: 25 April 2023
    Activity
    Burst Fission Gas Release (FGR) Benchmark of the Expert Group on Reactor Fuel Performance (EGRFP)

    This benchmark is organised to examine the models for fission gas release during anticipated operational occurrences (AOOs).

    Nuclear science Validation EGRPF WPRS Benchmark Reactor fuel performance …
    Published date: 7 March 2023
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