CHF prediction in rod bundles using round tube data

Fuente: Redalyc
Enregistré dans:
Détails bibliographiques
Auteur principal: W. F. Souza
Format: Artículo científico
Langue:en
Publié: Sociedade Brasileira de Proteção Radiológica - SBPR 2020
Sujets:
Accès en ligne:
Tags: Ajouter un tag
Pas de tags, Soyez le premier à ajouter un tag!
_version_ 1876466307316056064
author W. F. Souza
author_facet W. F. Souza
contents CHF prediction in rod bundles using round tube data W. F. Souza M. A. F. Veloso C. Pereira A. L. Costa Biología STHIP subchannel code Critical heat flux The present work concerns the use of 1995 CHF table for uniformly heated round tubes, developed jointly by Canadian and Russian researchers, for the prediction of critical heat flux in rod bundles geometries. Comparisons between measured and calculated critical heat fluxes indicate that this table can be applied to rod bundles provided that a suitable correction factor is employed. The tolerance limits associated with the departure from nucleate boiling ratio (DNBR) are evaluated by using statistical analysis. 2020 artículo científico 2319-0612 https://www.redalyc.org/articulo.oa?id=722280926015 en http://www.redalyc.org/revista.oa?id=7222 Brazilian Journal of Radiation Sciences application/pdf Sociedade Brasileira de Proteção Radiológica - SBPR Brazilian Journal of Radiation Sciences (Brasil) Num.3B Vol.8
format Artículo científico
id redalyc_722280926015
institution Redalyc
language en
publishDate 2020
publisher Sociedade Brasileira de Proteção Radiológica - SBPR
spellingShingle CHF prediction in rod bundles using round tube data
W. F. Souza
Biología
STHIP
subchannel code
Critical heat flux
CHF prediction in rod bundles using round tube data W. F. Souza M. A. F. Veloso C. Pereira A. L. Costa Biología STHIP subchannel code Critical heat flux The present work concerns the use of 1995 CHF table for uniformly heated round tubes, developed jointly by Canadian and Russian researchers, for the prediction of critical heat flux in rod bundles geometries. Comparisons between measured and calculated critical heat fluxes indicate that this table can be applied to rod bundles provided that a suitable correction factor is employed. The tolerance limits associated with the departure from nucleate boiling ratio (DNBR) are evaluated by using statistical analysis. 2020 artículo científico 2319-0612 https://www.redalyc.org/articulo.oa?id=722280926015 en http://www.redalyc.org/revista.oa?id=7222 Brazilian Journal of Radiation Sciences application/pdf Sociedade Brasileira de Proteção Radiológica - SBPR Brazilian Journal of Radiation Sciences (Brasil) Num.3B Vol.8
title CHF prediction in rod bundles using round tube data
topic Biología
STHIP
subchannel code
Critical heat flux
url https://www.redalyc.org/articulo.oa?id=722280926015