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Assessment of Look-up tables for the prediction of heat transfer coefficient distribution in rod bundles cooled by supercritical water

The result's identifiers

  • Result code in IS VaVaI

    <a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F00216208%3A11320%2F25%3AJW9SMJ4A" target="_blank" >RIV/00216208:11320/25:JW9SMJ4A - isvavai.cz</a>

  • Result on the web

    <a href="https://www.scopus.com/inward/record.uri?eid=2-s2.0-85199950934&doi=10.1016%2fj.net.2024.07.044&partnerID=40&md5=e8998b23b747f42f2bada946915d0cdc" target="_blank" >https://www.scopus.com/inward/record.uri?eid=2-s2.0-85199950934&doi=10.1016%2fj.net.2024.07.044&partnerID=40&md5=e8998b23b747f42f2bada946915d0cdc</a>

  • DOI - Digital Object Identifier

    <a href="http://dx.doi.org/10.1016/j.net.2024.07.044" target="_blank" >10.1016/j.net.2024.07.044</a>

Alternative languages

  • Result language

    angličtina

  • Original language name

    Assessment of Look-up tables for the prediction of heat transfer coefficient distribution in rod bundles cooled by supercritical water

  • Original language description

    The evaluation of available Look-Up Tables for prediction of heat transfer coefficient distribution in rod bundles cooled by supercritical water with the aim of their further use in computational analyses of various Fuel Assembles of Supercritical Water-Cooled Reactors is made. The comparison between the calculations based on Look-Up Tables with the values from empirical correlations and experimental data for smooth and wire-wrapped rod bundles was presented. The obtained results showed that Look-Up Table of the University of Ottawa, which was created to describe improved and deteriorated heat transfer regimes in round tubes, allows describing available data points with 30 % of the mean square deviation. It is noted that the presence of wire intensifies heat transfer exchange near pseudocritical temperature region but existing versions of Look-Up Tables cannot take into account this effect. Nevertheless, there is potential for further improvement in predicting the heat transfer coefficient using Look-Up Table by introducing additional correction factors. © 2024 Korean Nuclear Society

  • Czech name

  • Czech description

Classification

  • Type

    J<sub>SC</sub> - Article in a specialist periodical, which is included in the SCOPUS database

  • CEP classification

  • OECD FORD branch

    10201 - Computer sciences, information science, bioinformathics (hardware development to be 2.2, social aspect to be 5.8)

Result continuities

  • Project

  • Continuities

Others

  • Publication year

    2024

  • Confidentiality

    S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů

Data specific for result type

  • Name of the periodical

    Nuclear Engineering and Technology

  • ISSN

    1738-5733

  • e-ISSN

  • Volume of the periodical

    2024

  • Issue of the periodical within the volume

    2024

  • Country of publishing house

    US - UNITED STATES

  • Number of pages

    11

  • Pages from-to

    1-11

  • UT code for WoS article

  • EID of the result in the Scopus database

    2-s2.0-85199950934