A study on prediction methods of the critical heat flux for upward flow in a vertical narrow rectangular channel-Reference-Cited by-同舟云学术

A study on prediction methods of the critical heat flux for upward flow in a vertical narrow rectangular channel

Published:2015-12 Issue: Volume:294 Page:103-116
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Choi Gil Sik,Jeong Yong Hoon,Chang Soon Heung

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference23 articles.

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3. A comparison of critical heat flux in tubes and bilaterally heated annuli;Doerffer;Nucl. Eng. Des.,1997

4. Pressurized water reactor (PWR) project technical progress report, April 24, 1961 to June 23, 1961, WAPD-MRP-92;Goldman,1961

5. The 1995 Look-Up Table for critical heat flux in tubes;Groeneveld;Nucl. Eng. Des.,1996

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