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    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 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
    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: 9 November 2022
    Activity
    Expert Group on Physics of Reactor Systems (EGPRS)

    Under the guidance of the Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS), the Expert Group on Physics of Reactor Systems (EGPRS) performs specific tasks associa...

    Reactor physics Molten salt reactors Light water reactors EGPRS Pressurised heavy water reactors Reactor physics …
    Published date: 19 October 2022
    Joint project
    Dragon Project

    View of Dragon Reactor. Photo: AEA Technology.

    In 1959, twelve OECD countries began the Dragon Reactor Experiment (DRE) to build a reactor at Winfrith in Dorset, United Kingdom. The Dragon was the fi...

    Criticality safety Generation IV reactors Nuclear science Gas-cooled reactors Reactor physics …
    Published date: 14 October 2022
    NEA Document
    Existing Practices for Multi-physics Validation: Report on Sub-Task 3, Task Force 2
    NEA/NSC/R(2019)7

    The modelling and simulation of nuclear systems allow scientists and engineers to probe aspects of the operation of these systems beyond what has been precisely measured. This has numerous applicatio...

    Reactor physics Nuclear science WPRS Multiphysics Nuclear science Benchmark Reactor physics Multiphysics EGMUP …
    Published date: 11 October 2022
    News
    Discussing radiation shielding, novel accelerator experiments and radiation physics simulations

    The event gathered 129 participants from 75 international institutions.

    Reactor physics News brief Nuclear science Radiation shielding EGPRS WPRS Radiation transport and shielding Reactor physics …
    Published date: 6 October 2022
    Event
    SATIF-15: 15th workshop on Shielding aspects of Accelerators, Targets, and Irradiation Facilities (SATIF)
    20 - 23 September 2022
    Facility for Rare Isotope Beams at Michigan State University, East Lansing, Michigan (USA)

    The 15th workshop on Shielding aspects of Accelerators, Targets, and Irradiation Facilities (SATIF) is tentatively planned to be held in East Lansing, Michigan, USA, on 20-23 September 2022. The SATI...

    Radiation transport and shielding Radiological protection for occupational exposure at nuclear Installations Reactor physics
    Published date: 2 November 2021
    Activity
    SINBAD - Shielding Integral Benchmark Archive and Database

    The Shielding Integral Benchmark Archive and Database (SINBAD) database contains compilations for 46 reactor shielding, 31 fusion neutronics and 23 accelerator shielding experiments.

    Transport Experiments Radiation Validation Databases Benchmark Radiation transport and shielding Reactor physics …
    Published date: 4 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
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