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    Thermal hydraulics
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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 consists in a multi-staged code-to-code-to-data thermal hydraulics code validation...

    Thermal hydraulics Verification and validation Verification Validation Benchmark Reactor physics …
    Published date: 8 August 2022
    Activity
    Benchmark Based on NUPEC Pressurised Water Reactor (PWR) Subchannel and Bundle Tests (PSBT)

    An approach similar to the OECD/NRC Boiling Water Reactor Full-size Fine-mesh Bundle Tests (BFBT) Benchmark was adopted by dividing the benchmark activity into phases.

    Reactor physics Nuclear science Thermal hydraulics Multiphysics Benchmark Reactor physics Pressurised water reactors Multiphysics …
    Published date: 2 August 2022
    Activity
    Pressurised Water Reactor Main Steam-Line Break (MSLB) Benchmark

    This benchmark incorporated full 3-D modelling of the reactor core into system transient codes for best-estimate simulations of the interactions between reactor core behaviour and plant dynamics and ...

    Modelling and simulation Thermal hydraulics Verification and validation Nuclear safety research Uncertainty analysis Safety of components and structures Benchmark Thermal hydraulics and mechanics …
    Published date: 2 August 2022
    Activity
    OECD/NRC Benchmark based on NUPEC BWR Full-size Fine-mesh Bundle Tests (BFBT)

    NUPEC Boiling Water Reactor (BWR) Full-size Fine-mesh Bundle Test (BFBT) Benchmark

    Thermal hydraulics Reactor physics
    Published date: 2 August 2022
    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: 2 August 2022
    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: 2 August 2022
    Activity
    Liquid Metal Fast Reactor Core Thermal-Hydraulics Benchmark (LMFR T/H)

    The Liquid Metal Fast Reactor (LFMR) is one of the next generation reactor designs. This benchmark consists of steady-state numerical predictions of Texas A&M University (TAMU) separate effect tests ...

    Thermal hydraulics Verification and validation Verification Validation Benchmark Reactor physics …
    Published date: 19 July 2022
    Activity
    McMaster Core Thermal-Hydraulics Benchmark

    Building on the NEA BFBT and PSBT benchmarks, McMaster University, in collaboration with North Carolina State University, launched a CANDU thermal-hydraulic benchmark under the WPRS Expert Group on U...

    Nuclear science Thermal hydraulics Verification and validation Validation Benchmark Reactor physics …
    Published date: 19 July 2022
    Activity
    Boiling Water Reactor Turbine Trip (BWRTT) Benchmark

    The Boiling Water Reactor Turbine Trip (BWRTT) Benchmark was established to challenge the coupled system thermal-hydraulic/neutron kinetics codes against a Peach-Bottom-2 (a GE-designed BWR/4) turbin...

    Thermal hydraulics Verification and validation Verification Uncertainty quantification Uncertainty analysis Reactor physics …
    Published date: 19 July 2022
    News
    Specialists meeting on transient thermal-hydraulics in water cooled nuclear reactors

    The NEA Working Group on Analysis and Management of Accidents (WGAMA) organised a specialists’ meeting on transient thermal-hydraulics in water cooled nuclear reactors on 22-23 March 2022.

    News brief WGAMA Nuclear safety Accident analysis and management Thermal hydraulics …
    Published date: 6 April 2022
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