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    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
    Event
    WPRS Benchmarks Workshop 2023
    22 - 26 May 2023
    Zanhotel Europa, Via Cesare Boldini 11, Bologna, Italy + virtual option on ZOOM

    The annual Benchmark Workshops of the Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems will be hosted by the Italian National Agency for New Technologies, Energy and Sus...

    Reactor physics Nuclear science Multiphysics Nuclear science Benchmark Thermal hydraulics and mechanics Reactor physics Reactor fuel performance Multiphysics …
    Published date: 17 May 2023
    Event
    International School on Simulation of Nuclear Reactor Systems (SINUS)
    1 - 23 May 2023
    Online training & in-person event on 22-23 May 2023 in Bologna, Italy

    The NEA has organised the first International School on Simulation of Nuclear Reactor Systems (SINUS) on the topic of Reactor single- and multi-physics simulations based on Light Water Reactor (LWR) ...

    Nuclear science Education WPRS Nuclear science Reactor physics …
    Published date: 4 May 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
    News
    ICSBEP and IRPhEP Technical Review Group meetings

    The Technical Review Groups for both projects met at the NEA headquarters on 3-7 April 2023.

    News brief Nuclear science Criticality ICSBEP IRPhEP Reactor physics Reactor physics Criticality safety NSC SINBAD Nuclear science Benchmark …
    Published date: 24 April 2023
    Activity
    International Fuel Performance Experiments (IFPE) database

    International Fuel Performance Experiments (IFPE) is a data collection of nuclear fuel performance experiments for the purpose of code development and validation.

    Fuel studies Nuclear science Experiments EGRPF Databases Ancillary data Reactor physics …
    Published date: 19 April 2023
    Activity
    DATabase for IFpe (DATIF)

    Development started on DATIF, the DATabase for IFpe, in 2018 in order to enhance accessibility to the IFPE legacy collection of integral fuel performance experiments data, jointly put together by the...

    Nuclear fuel Physics Fuel studies NSC EGRFP Databases Ancillary data Reactor physics Integral experiments …
    Published date: 12 April 2023
    News
    Enhancing the NEA Shielding Integral Benchmark Archive and Database (SINBAD)

    EGPRS Task Force members met on 3 April 2023.

    Reactor physics News brief NSC Nuclear science Radiation shielding EGPRS SINBAD WPRS Reactor physics …
    Published date: 7 April 2023
    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: 6 April 2023
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