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    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
    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
    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
    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
    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
    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
    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
    NEA Document
    Coupled Neutronic/Thermal-Fluid Benchmark of the MHTGR-350 MW Core Design: Results for the Lattice Physics Exercises
    NEA/NSC/R(2019)6

    The purpose of this prismatic High Temperature Reactor (HTR) benchmark is to provide a solution set that can be used in future code benchmarking and to better understand the effects induced by the pr...

    English Nuclear science WPRS Multiphysics EGTHM Reactor physics Multiphysics EGMUP Reactor physics NSC EGPRS Nuclear science …
    Published date: 18 November 2021
    NEA Document
    NUPEC BWR Full-size Fine-mesh Bundle Test BFBT Benchmark - Volume III: Results of Phase I on Void Distribution
    NEA/NSC/R(2020)6

    In the past decade, a large amount of effort has been made towards the direct simulation of the boiling transition (BT) for Boiling Water Reactor (BWR) fuel bundles. This international benchmark, bas...

    English Boiling water reactors Nuclear science Nuclear safety WPRS Thermal hydraulics and mechanics EGTHM Reactor physics Reactor physics Nuclear science Benchmark …
    Published date: 1 June 2021
    NEA Document
    NUPEC BWR Full-size Fine-mesh Bundle Test BFBT Benchmark - Volume IV: Results of Phase II on Pressure Drop and Critical Power
    NEA/NSC/R(2020)7

    In the past decade, a large amount of effort has been made towards the direct simulation of the boiling transition (BT) for boiling water reactor (BWR) fuel bundles. This international benchmark, bas...

    English Boiling water reactors Nuclear science Nuclear safety WPRS EGTHM Reactor physics Reactor physics Nuclear science Benchmark …
    Published date: 2 December 2021
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