Conference Proceedings Paper
Measurement of Subcooled Boiling Pressure Drop and Local Heat Transfer Coefficient in Horizontal Channels Under LPLF Conditions
NURETH-14 - 2011 September 25-30
P.K. Baburajan (Atomic Energy Regulatory Board, India)
S.K. Gupta (Atomic Energy Regulatory Board, India)
Govind Singh Bisht (Indian Institute of Technology Bombay)
S.V. Prabhu (Indian Institute of Technology Bombay)
Horizontal flow is commonly encountered in boiler tubes, refrigerating equipments and nuclear
reactor fuel channels of pressurized heavy water reactors (PHWR). Study of horizontal flow under
low pressure and low flow (LPLF) conditions is important in understanding the nuclear core
behavior during situations like LOCA (Loss of coolant accidents). In the present work,
experimental measurements of local heat transfer coefficient and pressure drop are carried out in a
horizontal channel under LPLF conditions of sub-cooled boiling. Infrared thermography is used for
the measurement of local wall temperature to estimate the heat transfer coefficient in single phase
and two phase flows with water as the working medium at atmospheric pressure. Correlation for
single phase diabatic pressure drop ratio (diabatic to adiabatic) as a function of viscosity ratio (wall
temperature to fluid temperature) is presented. Correlation for pressure drop under sub-cooled
boiling conditions as a function of Bo (Boiling number) and Ja (Jacob number) is obtained.
Correlation for single phase heat transfer coefficient in the developing region is presented as a
function of z/d (ratio of axial length of the test section to diameter). Correlation for two-phase heat transfer coefficient under
sub-cooled boiling condition is presented as a function of Bo, Ja and Pr (Prandtl number). Correlation
between heat transfer coefficient and friction factor is obtained by applying Reynolds analogy.
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