Development of a dimensionless rod-bundle CHF correlation based on stepwise regression method, Part I: determination of the basic form with CHF data obtained with uniform axial heat flux profile-Reference-Cited by-同舟云学术

Development of a dimensionless rod-bundle CHF correlation based on stepwise regression method, Part I: determination of the basic form with CHF data obtained with uniform axial heat flux profile

Published:2020-08 Issue: Volume:143 Page:107454
ISSN:0306-4549
Container-title:Annals of Nuclear Energy
language:en
Short-container-title:Annals of Nuclear Energy

Author:

Pang Bo^ORCID,Yin Yuan

Funder

Natural Science Foundation of Guangdong Province

Natural Science Foundation of Shenzhen University

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference18 articles.

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3. Cheng, X., Müller, U., 2003. Review on critical heat flux in water cooled reactors. Scientific Report FZKA 6825.

4. Applied Regression Analysis;Draper,1981

5. An improved version of the generalized correlation of critical heat flux for the forced convective boiling in uniformly heated vertical tubes;Katto;Int. J. Heat Mass Transf.,1984

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