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This work is licensed under a Creative Commons Attribution-NonCommercial 4.0 International License
Article
Author(s)
Yuzhou Chen, Keming Bi, Minfu Zhao, Chunsheng Yang and Kaiwen Du
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DOI:10.17265/1934-8975/2016.04.001
Affiliation(s)
Department of Reactor Engineering Research and Design, China Institute of Atomic Energy, Beijing 102413, China
ABSTRACT
During last 45 years, two
groups of the experimental data on critical heat flux were obtained in bare
tubes, covering the pressures from atmosphere to near-critical point. One group
of the data were obtained in the inner diameter of 2.32, 5.16, 8.05, 10.0 and
16.0 mm, respectively, with the ranges of pressure of 0.1-1.92 MPa, velocity of
1.47-23.3 m/s, local subcooling of 3.7-108.7 °C and heat flux of up
to 38.3 MW/m2. Another group of the data were obtained in the inner
diameter of 4.62, 7.98 and 10.89 mm, respectively, with the ranges of pressure
of 1.7-20.6 MPa, mass flux of 454-4,055 kg/(m2·s) and inlet
subcooling of 53-361 °C. The results showed complicated effects of the
pressure, mass flux, subcooling and diameter on the critical heat flux. They
were formulated by two empirical correlations. A mechanistic model on the limit
of heat transfer capability from the bubbly layer to the subcooled core was also
proposed for all the results.
KEYWORDS
Critical heat flux, near-critical pressure, atmosphere, subcooled water.
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