Subcooled Flow Boiling Critical Heat Flux (CHF) and Its Application to Fusion Energy Components. Part II. A Review of Microconvective, Experimental, and Correlational Aspects-Reference-Cited by-同舟云学术

Subcooled Flow Boiling Critical Heat Flux (CHF) and Its Application to Fusion Energy Components. Part II. A Review of Microconvective, Experimental, and Correlational Aspects

Published:1985-01 Issue:1 Volume:7 Page:31-52
ISSN:0748-1896
Container-title:Fusion Technology
language:en
Short-container-title:Fusion Technology

Author:

Boyd Ronald D.¹

Affiliation:

1. Sandia National Laboratories, Division 1513 P.O. Box 5800, Albuquerque, New Mexico 87185

Publisher

Informa UK Limited

Subject

General Engineering

Link

https://www.tandfonline.com/doi/pdf/10.13182/FST85-A24516

Reference111 articles.

1. Subcooled Flow Boiling Critical Heat Flux (CHF) and Its Application to Fusion Energy Components. Part I. A Review of Fundamentals of CHF and Related Data Base

2. An analytical study of the thermally induced two-phase flow instabilities including the effect of thermal non-equilibrium

3. Superheating in nucleate boiling calculated by the heterogeneous nucleation theory

4. Motion of a contact line

5. Rayleigh–Taylor stability with mass and heat transfer

Cited by 31 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Vapor Agglomerates and Dry Spots as Precursors of the Subcooled Liquid Boiling Crisis in a Channel;High Temperature;2021-03

2. Thermal management and temperature uniformity enhancement of electronic devices by micro heat sinks: A review;Energy;2021-02

3. Critical heat flux in a multi-minichannel heat sink. Effect of the heated length-on-diameter ratio;Journal of Physics: Conference Series;2017-01

4. Critical Heat Flux in Flow Boiling—Review of the Current Understanding and Experimental Approaches;Heat Transfer Engineering;2016-09-14

5. Current status of CHF predictions using CFD modeling technique and review of other techniques especially for non-uniform axial and circumferential heating profiles;Annals of Nuclear Energy;2014-08