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
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Czech description
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Classification
Type
J<sub>SC</sub> - Article in a specialist periodical, which is included in the SCOPUS database
CEP classification
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OECD FORD branch
10201 - Computer sciences, information science, bioinformathics (hardware development to be 2.2, social aspect to be 5.8)
Result continuities
Project
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Continuities
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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
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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
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EID of the result in the Scopus database
2-s2.0-85199950934