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    IRPhE Handbook 2019 Edition - Contents

    IRPhE Handbook 2019 Edition - Contents

    Verification and validation Verification Uncertainty quantification Uncertainty analysis Reactor physics …
    Published date: 30 September 2020
    Activity
    Expert Group on Improvement of Integral Experiments Data for Minor Actinide Management (EGIEMAM-II)

    The expert group works in co-ordination with Working Party on Scientific Issues of Reactor Systems (WPRS) [including the IRPhE Project], Working Party on Scientific Issues of the Fuel Cycle (WPFC) an...

    WPEC NSC Nuclear science Experiments Actinides WPRS Nuclear fuel cycle Reactor physics Fuel cycle physics and chemistry Integral experiments Minor actinides …
    Published date: 9 March 2020
    News
    Scientific issues of nuclear reactor systems

    NEA Working Party on Scientific Issues of Reactor Systems (WPRS) annual meeting, 19-21 February 2020.

    Reactor physics News brief Nuclear science SINBAD Reactor physics …
    Published date: 4 March 2020
    Activity
    Expert Group on Radiation Transport and Shielding (EGRTS)

    Under the guidance of the Working Party on Scientific Issues of Reactor Systems (WPRS), the expert group performed specific tasks associated with radiation transport and shielding aspects of current ...

    EGRTS State-of-the-art report Benchmark Reactor physics
    Published date: 3 March 2020
    Subtopic
    Reactor physics

    Questions relating to the space, time end energy distribution of neutrons and radiation in different media are the domain of reactor physics.

    Reactor physics Verification and validation Fast reactor Benchmark Advanced reactors Reactor physics …
    Published date: 2 December 2019
    News
    ICSBEP, SINBAD AND IRPhEP Technical Review Group meetings

    ICSBEP, SINBAD AND IRPhEP Technical Review Group meetings

    News brief Criticality safety Nuclear science SINBAD Reactor physics …
    Published date: 18 November 2019
    Event
    Benchmark for Uncertainty Analysis in Best-Estimate Modelling (UAM) for Design, Operation and Safety Analysis of LWRs - Workshop 13 (LWR-UAM-13)
    13 - 17 May 2019
    Oak Ridge, United States
    Boiling water reactors Light water reactors Reactor physics Modelling and simulation Reactor physics Verification and validation Verification Validation Uncertainty analysis Benchmark Pressurised water reactors …
    Published date: 18 December 2020
    NEA Document
    A Code to Code Benchmark for High-Temperature Gas-Cooled Reactor Fuel Element Depletion
    NEA/NSC/R(2019)1

    The high-temperature gas-cooled reactor (HTGR) is a Generation IV reactor concept that uses a graphitemoderated gas-cooled nuclear reactor with a once-through uranium fuel cycle. This design permits ...

    English Nuclear fuel Fuel studies Generation IV reactors Nuclear science WPRS Reactor physics Multiphysics EGMUP Reactor physics Cogeneration NSC Gas-cooled reactors EGPRS Nuclear science Benchmark …
    Published date: 18 January 2019
    Event
    Benchmark for Uncertainty Analysis in Best-Estimate Modelling (UAM) for Design, Operation and Safety Analysis of LWRs - Workshop 12 (LWR-UAM-12)
    16 - 17 May 2018
    Lucca, Italy
    Boiling water reactors Light water reactors Reactor physics Modelling and simulation Reactor physics Verification and validation Verification Validation Uncertainty analysis Benchmark Pressurised water reactors …
    Published date: 18 December 2020
    NEA Document
    NEA Benchmark of the Modular High-Temperature Gas-Cooled Reactor 350 MW Core DesignVolumes I and II
    NEA/NSC/R(2017)4
    English Reactor physics NSC Nuclear science EGPRS WPRS Nuclear science EGTHM Reactor physics EGMUP …
    Published date: 6 December 2017
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