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    Event
    Benchmark for Uncertainty Analysis in Best-Estimate Modelling (UAM) for Design, Operation and Safety Analysis of LWRs - Workshop 10 (LWR-UAM-10)
    1 - 3 June 2016
    Villigen, Switzerland
    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
    Event
    Benchmark for Uncertainty Analysis in Best-Estimate Modelling (UAM) for Design, Operation and Safety Analysis of LWRs - Workshop 11 (LWR-UAM-11)
    10 - 12 May 2017
    Erlangen, Germany
    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
    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
    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 Reactor physics Multiphysics Reactor physics Cogeneration NSC Gas-cooled reactors 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 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
    News
    ICSBEP, SINBAD AND IRPhEP Technical Review Group meetings

    ICSBEP, SINBAD AND IRPhEP Technical Review Group meetings

    News brief Criticality safety Nuclear science Reactor physics
    Published date: 18 November 2019
    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
    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
    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 Reactor physics
    Published date: 4 March 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
    Activity
    DATabase for IFpe (DATIF)

    DATIF, the DATabase for IFpe, was first developed in 2018 in order to enhance accessibility to the IFPE legacy collection of integral fuel performance experiments data, jointly put together by the NE...

    Nuclear fuel Physics Fuel studies NSC EGRFP Databases Ancillary data Reactor physics Integral experiments …
    Published date: 23 July 2020
    Activity
    International Fuel Performance Experiments (IFPE) database

    International Fuel Performance Experiments (IFPE) is the public domain database on 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 August 2020
    Activity
    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
    Subtopic
    Multiphysics

    Multiphysics are simulations using computer applications or software to couple multiple physical events in order to predict or validate the physical real-world outcome.

    Multi-physics simulations Nuclear science Benchmark Reactor physics Multiphysics …
    Published date: 16 October 2020
    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: 6 November 2020
    Publications and Reports
    Physics of Plutonium Recycling - Volume III

    The quality of the isotopic composition of plutonium fuel degrades as the number of recycles increases in thermal reactors, requiring an increase in the total loading necessary in mixed plutonium-ura...

    English Nuclear science Plutonium Liquid metal reactors Advanced reactors Reactor physics Recycling and reuse Reactor physics NSC Gas-cooled reactors Fuel cycle technology Fuel cycle physics and chemistry Pressurised water reactors …
    Published date: 17 November 2020
    Other
    Third Information Exchange Meeting on the Nuclear Production of Hydrogen - Programme

    Third Information Exchange Meeting on the Nuclear Production of Hydrogen including Second HTTR Workshop, Japan Atomic Energy Agency (JAEA), Oarai, Japan, 5 - 7 October 2005 - Programme

    Nuclear science Multiphysics Reactor physics
    Published date: 24 November 2020
    Other
    First Information Exchange Meeting on the Nuclear Production of Hydrogen - Programme and abstracts

    First Information Exchange Meeting on the Nuclear Production of Hydrogen, Paris, France, 2-3 October, 2000 - Programme and abstracts

    Nuclear science Multiphysics Reactor physics
    Published date: 24 November 2020
    Subtopic
    Thermal hydraulics and mechanics

    Thermal hydraulics and mechanics deals with the physics and mechanics of the flow and energetic transfer of liquids, and its interactions with the structures around them in large complex systems, suc...

    Reactor physics Nuclear science Thermal hydraulics Verification and validation Verification Validation Benchmark Reactor physics …
    Published date: 10 December 2020
    Subtopic
    Reactor fuel performance

    Understanding fuel performance is a key condition for successful reactor operation. Scientific knowledge in this domain was conceived by experimental tests encoded into software routines to ensure ac...

    Reactor physics Fuel studies Nuclear science Reactor physics
    Published date: 10 December 2020
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