Evaluation of subcooled critical heat flux correlations for tubes with and without internal twisted tapes-Reference-Cited by-同舟云学术

Evaluation of subcooled critical heat flux correlations for tubes with and without internal twisted tapes

Published:1996-06 Issue:1-2 Volume:163 Page:225-239
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Inasaka F.,Nariai H.

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

Reference34 articles.

1. Heavy water moderated power reactors;Babcock,1962

2. Subcooled water flow boiling experiments under uniform high heat flux conditions;Boyd;Fusion Technol.,1988

3. EUR-2432.d;BurcK;EURATOM,1965

4. Preliminary remarks on high heat flux CHF in subcooled water flow boiling;Celata;Int. J. Heat Technol.,1990

5. Burnout in highly subcooled flow boiling in small diameter tubes;Celata,1991

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