Critical heat flux of water in vertical round tubes at low pressure and low flow conditions-Reference-Cited by-同舟云学术

Critical heat flux of water in vertical round tubes at low pressure and low flow conditions

Published:2000-06 Issue:1-2 Volume:199 Page:49-73
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Kim Hong Chae,Baek Won-Pil,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

Reference32 articles.

1. Baek, W.P., Moon, S.K., Chang, S.H., 1995. A modified CHF correlation for low flow of water at low pressures. In: Proceedings of the First International Symposium on Two-Phase Flow Modeling and Experimentation, Rome, Italy, 9–11 October, pp. 853–858.

2. Baek, W.P., Kim, H.G., Chang, S.H., 1997. KAIST critical heat flux correlation for water flow in vertical round tubes, NUTHOS-5, Paper No. AA5.

3. Studies of burnout in boiling heat transfer;Bennett;Trans. Inst. Chem. Eng.,1967

4. Burnout in boiling heat transfer, Part II: subcooled and low quality forced convection systems;Bergles;Nucl. Safety,1977

5. Bowring, R.W., 1972. A simple but accurate round tube uniform heat flux dryout correlation over the pressure range 0.7–17.0 MN m−2, AEEW-R-789.

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