Conference Proceedings Paper
Subcooled Boiling Critical Heat Flux of Water in Lower Flow Upward in Tubes for Pressure up to 22 MPa
NURETH-14 - 2011 September 25-30
Yuzhou Chen (China Institute of Atomic Energy)
Chunsheng Yang (China Institute of Atomic Energy)
Minfu Zhao (China Institute of Atomic Energy)
Keming Bi (China Institute of Atomic Energy)
Kaiwen Du (China Institute of Atomic Energy)
Shuming Zhang (China Institute of Atomic Energy)
An experiment of critical heat flux was conducted in an inconel tube of inner diameter of 7.98 mm and heating length of 0.8 m with water flowing upward, covering the ranges of pressure of 1.96 – 20.4 MPa, mass flux of 476 – 1653 kg/m2s, inlet subcooling of 49 – 346 K and exit subcooling of 1 – 158 K. Based on the experimental result, an empiric correlation was formulated and the parametric trends were studied systematically. A physical model was proposed with assumption of critical thickness of bubbly layer.
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