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    NEA Document
    Computational Fluid Dynamics for Nuclear Reactor Safety Applications-6 (CFD4NRS-6): Workshop Proceedings
    NEA/CSNI/R(2017)20

    The present report summarises the 6th workshop on Computational Fluid Dynamics for Nuclear Reactor Safety Applications (CFD4NRS-6) in the biennial series, supported by the Nuclear Energy Agency Worki...

    English WGAMA Nuclear safety research CSNI Proceedings …
    Published date: 6 May 2019
    NEA Document
    Informing Severe Accident Management Guidance and Actions for Nuclear Power Plants through Analytical Simulation
    NEA/CSNI/R(2017)16

    This report by the Working Group on Analysis and Management of Accidents (WGAMA) summarises the first Nuclear Energy Agency (NEA) project to address the topic of severe accident management guidance (...

    English WGAMA Accident analysis and management Nuclear safety research CSNI …
    Published date: 2 July 2018
    NEA Document
    Post-BEMUSE Reflood Model Input Uncertainty Methods (PREMIUM) Benchmark: Final Report
    NEA/CSNI/R(2016)18

    PREMIUM is the follow-up of a series of projects promoted by NEA/CSNI and focused on the issue of best estimate plus uncertainty (BEPU) analysis of thermo-hydraulic accident scenarios in nuclear plan...

    English WGAMA Nuclear safety research CSNI Benchmark …
    Published date: 24 August 2017
    NEA Document
    A State-of-the-Art Report on Scaling in System Thermal-hydraulics Applications to Nuclear Reactor Safety and Design
    NEA/CSNI/R(2016)14

    The present document deals with scaling in nuclear-system thermal hydraulics (SYS TH), including the connection with nuclear-reactor safety technology (NST). Scaling has constituted “an issue” since ...

    English WGAMA Nuclear safety research CSNI
    Published date: 1 March 2017
    NEA Document
    State-of-the-Art Report on Molten Corium Concrete Interaction and Ex-Vessel Molten Core Coolability
    NEA/CSNI/R(2016)15

    Since 2002, the Nuclear Energy Agency (NEA) has sponsored the Melt Coolability and Concrete Interaction (MCCI) co-operative project in two phases in order to investigate ex-vessel melt coolability an...

    English WGAMA Nuclear safety research CSNI
    Published date: 1 January 2017
    NEA Document
    PREMIUM: A Benchmark on the Quantification of the Uncertainty of the Physical Models in the System Thermal-hydraulic Codes. Methodologies and Data Review
    NEA/CSNI/R(2016)9

    The objective of the Post-BEMUSE Reflood Model Input Uncertainty Methods (PREMIUM) benchmark is to progress on the issue of the quantification of the uncertainty of the physical models in system ther...

    English WGAMA Nuclear safety research CSNI Benchmark …
    Published date: 28 April 2016
    NEA Document
    Review of Uncertainty Methods for Computational Fluid Dynamics Application to Nuclear Reactor Thermal Hydraulics
    NEA/CSNI/R(2016)4

    Single-phase computational fluid dynamics (CFD) is used more and more for design and safety issues related to light-water reactor (LWR) thermal hydraulics. Over the past ten years, the Working Group ...

    English CFD WGAMA Nuclear safety research CSNI …
    Published date: 1 February 2016
    NEA Document
    Benchmarking of Fast-running Software Tools Used to Model Releases During Nuclear Accidents
    NEA/CSNI/R(2015)19

    The objective of this joint WGAMA-WPNEM activity was to benchmark software tools used to estimate consequences of accidents at nuclear facilities. Two aspects of accident consequences were considered...

    English WGAMA WPNEM Nuclear safety research CSNI Benchmark …
    Published date: 1 January 2016
    NEA Document
    Computational Fluid Dynamics for Nuclear Reactor Safety-5 (CFD4NRS-5): Workshop Proceedings
    NEA/CSNI/R(2016)1
    This present workshop was held in Zurich, Switzerland on 9-11 September 2014. It is the 5th workshop on Computational Fluid Dynamics for Nuclear Reactor Safety (CFD4NRS-5), in the biennial series of...
    English CFD WGAMA CSNI Proceedings …
    Published date: 1 January 2016
    NEA Document
    Ability of Current Advanced Codes to Predict In-Vessel Core Melt Progression and Degraded Core Coolability: Benchmark Exercise on the Three Mile Island-2 Plant – Final Report
    NEA/CSNI/R(2015)3

    Based on the conclusions of the previous benchmark exercise, the NEA Working Group on Analysis and Management of Accidents (WGAMA) felt it worthwhile to extend the accident analysis scope by examinin...

    English WGAMA Nuclear safety research CSNI Benchmark …
    Published date: 19 June 2015
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