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    Event
    21st Meeting of the Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS)
    19 - 23 February 2024
    NEA headquarters (46, quai Alphonse Le Gallo, 92100 Boulogne-Billancourt, France)

    Under the guidance of the Nuclear Science Committee (NSC), the Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS) studies the reactor physics, fuel performance, an...

    Nuclear science EGRFP EGRRS WPRS Multiphysics Radiation transport and shielding Thermal hydraulics and mechanics EGTHM Reactor physics Reactor fuel performance EGMUP NSC Nuclear science …
    Published date: 18 July 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: 19 July 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: 18 July 2023
    News
    Challenging state-of-the art thermal hydraulics simulation capabilities for high temperature gas-cooled reactors

    Kick-off workshop of the thermal hydraulic code validation benchmark for high temperature gas-cooled reactors using High Temperature Test Facility (HTTF) data.

    News brief Nuclear science WPRS Thermal hydraulics and mechanics EGTHM Reactor physics Reactor physics NSC Thermal hydraulics Nuclear science Benchmark …
    Published date: 16 June 2023
    News
    Training the next generation of nuclear simulation specialists

    The first International School on Simulation of Nuclear Reactor Systems (SINUS) took place on 22-23 May 2023.

    Reactor physics News brief Nuclear science Education WPRS Nuclear science Reactor physics …
    Published date: 14 June 2023
    News
    Benchmarking state-of-the art nuclear reactor simulations

    The annual WPRS Benchmarks Workshops took place on 22-26 May 2023 in Bologna, Italy.

    Reactor physics Nuclear science WPRS Multiphysics Nuclear science Benchmark Thermal hydraulics and mechanics Reactor physics Reactor fuel performance Multiphysics …
    Published date: 13 June 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
    Activity
    Expert Group on Reactor Core Thermal-Hydraulics and Mechanics (EGTHM)

    Created in 2019, under the guidance of the Working Party on Scientific Issues of Reactor Systems (WPRS) the expert group will perform specific tasks associated with core thermal-hydraulics aspects of...

    Reactor physics Sodium-cooled reactor Molten salt reactors Light water reactors Thermal hydraulics WPRS Reactor physics …
    Published date: 8 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
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