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    Computational Fluid Dynamics Prediction of Heat Transfer in Rod Bundles With Water at Supercritical Pressure

    Source: Journal of Nuclear Engineering and Radiation Science:;2016:;volume( 002 ):;issue: 001::page 11011
    Author:
    Pucciarelli, Andrea
    ,
    Ambrosini, Walter
    DOI: 10.1115/1.4031201
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: The paper further explores the application of computational fluid dynamics (CFD) codes for the study of the heattransfer phenomena involved when working with fluids at supercritical pressure; bundle analysis is considered here in particular. As for previous simulations performed by the authors considering heattransfer deterioration inside heated tubes, this application points out the limited capabilities of the most commonly used Reynoldsaveraged Navier–Stokes models when approaching the heattransfer deterioration phenomenon. It must be noted that some of the considered experimental conditions, which are very close to the pseudocritical temperature, represent at the same time one of the most challenging situations for the CFD codes and a very common situation if supercritical watercooled reactors (SCWRs) will be developed. Improvements of the currently available turbulence models are then needed. The paper analyzes the most likely causes of the observed insufficient quality of the obtained predictions. In addition to comparing the measured and calculated wall temperature trends, the effect of the presence of the spacer grids on the turbulent flow is considered. Spacers are in fact very important to assure the structural stability of fuel, though they also affect the flow, generally improving the turbulence conditions in their neighborhood and slightly impairing it in the downstream region. A comparison between predictions performed including or not including the spacers is also performed.
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      Computational Fluid Dynamics Prediction of Heat Transfer in Rod Bundles With Water at Supercritical Pressure

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    http://yetl.yabesh.ir/yetl1/handle/yetl/162190
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    contributor authorPucciarelli, Andrea
    contributor authorAmbrosini, Walter
    date accessioned2017-05-09T01:32:10Z
    date available2017-05-09T01:32:10Z
    date issued2016
    identifier issn2332-8983
    identifier otherNERS_2_1_011011.pdf
    identifier urihttp://yetl.yabesh.ir/yetl/handle/yetl/162190
    description abstractThe paper further explores the application of computational fluid dynamics (CFD) codes for the study of the heattransfer phenomena involved when working with fluids at supercritical pressure; bundle analysis is considered here in particular. As for previous simulations performed by the authors considering heattransfer deterioration inside heated tubes, this application points out the limited capabilities of the most commonly used Reynoldsaveraged Navier–Stokes models when approaching the heattransfer deterioration phenomenon. It must be noted that some of the considered experimental conditions, which are very close to the pseudocritical temperature, represent at the same time one of the most challenging situations for the CFD codes and a very common situation if supercritical watercooled reactors (SCWRs) will be developed. Improvements of the currently available turbulence models are then needed. The paper analyzes the most likely causes of the observed insufficient quality of the obtained predictions. In addition to comparing the measured and calculated wall temperature trends, the effect of the presence of the spacer grids on the turbulent flow is considered. Spacers are in fact very important to assure the structural stability of fuel, though they also affect the flow, generally improving the turbulence conditions in their neighborhood and slightly impairing it in the downstream region. A comparison between predictions performed including or not including the spacers is also performed.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleComputational Fluid Dynamics Prediction of Heat Transfer in Rod Bundles With Water at Supercritical Pressure
    typeJournal Paper
    journal volume2
    journal issue1
    journal titleJournal of Nuclear Engineering and Radiation Science
    identifier doi10.1115/1.4031201
    journal fristpage11011
    journal lastpage11011
    treeJournal of Nuclear Engineering and Radiation Science:;2016:;volume( 002 ):;issue: 001
    contenttypeFulltext
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