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    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
    NEA Document
    MOx Depletion Calculation Benchmark
    NEA/NSC/R(2016)3

    In 2013, the Expert Group on Reactor Physics and Advanced Nuclear Systems (EGRPANS) published a report that investigated fuel depletion effects in a pressurised water reactor (PWR). This was entitled...

    English Reactor physics NSC Nuclear science EGPRS WPRS Nuclear science Reactor physics …
    Published date: 14 June 2016
    NEA Document
    International Benchmark on Pressurised Water Reactor Sub-channel and Bundle Tests - Volume III: Departure from nucleate boiling
    NEA/NSC/R(2015)7

    The need to refine models for best-estimate calculations based on good-quality experimental data has arisen for various nuclear applications. One of the most extensive and valuable databases availabl...

    English Nuclear science WPRS Multiphysics Thermal hydraulics and mechanics EGTHM Reactor physics Reactor physics NSC Nuclear science Benchmark Pressurised water reactors …
    Published date: 2 October 2015
    NEA Document
    International Benchmark on Pressurised Water Reactor Sub-channel and Bundle Tests - Volume II: Benchmark results of phase I Void distribution
    NEA/NSC/R(2015)4

    The objective of the benchmark was twofold. First, the benchmark aimed to evaluate currently available computational approaches in an effort to understand the strengths and weaknesses of current ther...

    English Nuclear science WPRS Multiphysics Thermal hydraulics and mechanics EGTHM Reactor physics Reactor physics NSC Nuclear science Benchmark …
    Published date: 24 June 2015
    NEA Document
    Benchmark for Neutronic Analysis of Sodium-cooled Fast Reactor Cores with Various Fuel Types and Core Sizes
    NEA/NSC/R(2015)9

    Sodium fast reactors offer the most promising type of reactors to achieve such Generation IV goals at a reasonable time scale given the experience accumulated over the years. However, it is recognise...

    English Nuclear fuel Fuel studies Generation IV reactors Nuclear science WPRS Reactor physics Reactor physics Sodium-cooled reactor NSC EGPRS Nuclear science Benchmark …
    Published date: 5 November 2015
    Subtopic
    Accident-tolerant fuels

    Accident-tolerant fuels may offer opportunities to enhance the safety and competitiveness of commercial nuclear power plants.

    Accident Tolerant Fuels
    Published date: 16 December 2019
    Subtopic
    Criticality safety

    Criticality safety relates to accident prevention and protection from an uncontrolled nuclear fission chain reaction, or a criticality accident.

    Criticality safety
    Published date: 2 December 2019
    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 Thermal hydraulics and mechanics Reactor physics …
    Published date: 10 December 2020
    NEA Document
    Burn-up Credit Criticality Studies: Benchmark Analyses for Pressurised Water Reactors
    NEA/NSC/R(2016)1
    English Nuclear science Criticality WPNCS WPRS Multiphysics Reactor physics Multiphysics EGMUP Reactor physics Criticality safety NSC Nuclear science …
    Published date: 23 February 2016
    Joint project
    Thermodynamics of Advanced Fuels – International Database (TAF-ID) public version

    The TAF-ID public version contains only data already published in open literature. Currently, the following systems are available in the public version:

    • oxide-carbide fuel (U-Pu-O-C, released Decemb...
    Material science Fuel studies Nuclear science Materials science Thermodynamics Thermodynamic data Databases TAF-ID Codes and programs …
    Published date: 23 February 2023
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