Thermal-hydraulics validation of CFD code for light water nuclear reactors against benchmark experimental results

Thermal-hydraulics validation of CFD code for light water nuclear reactors against benchmark experimental results

The cooling of a nuclear reactor depends on a suitable fluid flow pattern among its fuel elements aiming the removal of heat produced in the fuel. In case of light water reactors, an excess of heat drives the fluid to change its phase from liquid to vapor, significantly reducing its capacity to remo...

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Bibliographic Details
Main Authors: Deiglys Borges Monteiro, Duvan Alejandro Castellanos Gonzalez, José Rubens Maiorino
Format: Article
Language:English
Published: Brazilian Radiation Protection Society (Sociedade Brasileira de Proteção Radiológica, SBPR) 2021-07-01
Series:Brazilian Journal of Radiation Sciences
Subjects:
benchmark
cfd
subchannel
fuel rod
validation
Online Access:https://bjrs.org.br/revista/index.php/REVISTA/article/view/1403
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