During a severe accident, ex-vessel cooling may pose a risk for larger-powered reactors. The current in-vessel retention (IVR) (through ex-vessel cooling) capability may not be sufficient for the larger-powered reactors, and critical heat flux (CHF) conditions may eventually lead to vessel failure. A manner in which the CHF can be increased is by applying a structured surface design on the outer surface of the reactor pressure vessel (RPV). A simple design proposed in this work is the pin–fin. An experimental investigation was performed to observe the effect of the pin–fin on CHF with a downward-facing heated surface in flow boiling conditions. A reduced pressure of approximately 0.05 MPa allowed for saturation at approximately 81 °C. A range of flow rates corresponding to mass flux of 202–1456 kg/m2 s were applied in the experiments. The results showed an increase in the CHF when compared to a bare surface. An average CHF enhancement of 61% was observed from the finned surface. An enhancement of approximately 19% was observed in the heat transfer coefficient. As seen in nanoparticle/nanofluid enhancement, an increase in the CHF also leads to an increase in the superheat. Even though an increase in the CHF had been observed, the CHF for the finned and bare surfaces occurred at approximately similar superheat.
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Research-Article
An Experimental Study on Flow Boiling Heat Transfer From a Downward-Facing Finned Surface and Its Effect on Critical Heat Flux
A. R. Khan,
A. R. Khan
Department of Nuclear Engineering
and Management,
School of Engineering,
The University of Tokyo,
7-3-1 Hongo,
Bunkyo-ku 113-8654, Tokyo, Japan
e-mail: ark8@njit.edu
and Management,
School of Engineering,
The University of Tokyo,
7-3-1 Hongo,
Bunkyo-ku 113-8654, Tokyo, Japan
e-mail: ark8@njit.edu
Search for other works by this author on:
N. Erkan,
N. Erkan
Nuclear Professional School,
School of Engineering,
The University of Tokyo,
2-22 Shirakata,
Tokai-mura 319-1188, Ibaraki, Japan
e-mail: erkan@vis.t.u-tokyo.ac.jp
School of Engineering,
The University of Tokyo,
2-22 Shirakata,
Tokai-mura 319-1188, Ibaraki, Japan
e-mail: erkan@vis.t.u-tokyo.ac.jp
Search for other works by this author on:
K. Okamoto
K. Okamoto
Nuclear Professional School,
School of Engineering,
The University of Tokyo,
2-22 Shirakata, Tokai-mura 319-1188, Ibaraki, Japan
e-mail: okamoto@n.t.u-tokyo.ac.jp
School of Engineering,
The University of Tokyo,
2-22 Shirakata, Tokai-mura 319-1188, Ibaraki, Japan
e-mail: okamoto@n.t.u-tokyo.ac.jp
Search for other works by this author on:
A. R. Khan
Department of Nuclear Engineering
and Management,
School of Engineering,
The University of Tokyo,
7-3-1 Hongo,
Bunkyo-ku 113-8654, Tokyo, Japan
e-mail: ark8@njit.edu
and Management,
School of Engineering,
The University of Tokyo,
7-3-1 Hongo,
Bunkyo-ku 113-8654, Tokyo, Japan
e-mail: ark8@njit.edu
N. Erkan
Nuclear Professional School,
School of Engineering,
The University of Tokyo,
2-22 Shirakata,
Tokai-mura 319-1188, Ibaraki, Japan
e-mail: erkan@vis.t.u-tokyo.ac.jp
School of Engineering,
The University of Tokyo,
2-22 Shirakata,
Tokai-mura 319-1188, Ibaraki, Japan
e-mail: erkan@vis.t.u-tokyo.ac.jp
K. Okamoto
Nuclear Professional School,
School of Engineering,
The University of Tokyo,
2-22 Shirakata, Tokai-mura 319-1188, Ibaraki, Japan
e-mail: okamoto@n.t.u-tokyo.ac.jp
School of Engineering,
The University of Tokyo,
2-22 Shirakata, Tokai-mura 319-1188, Ibaraki, Japan
e-mail: okamoto@n.t.u-tokyo.ac.jp
1Corresponding author.
Contributed by the Heat Transfer Division of ASME for publication in the JOURNAL OF HEAT TRANSFER. Manuscript received September 26, 2016; final manuscript received June 15, 2017; published online August 29, 2017. Assoc. Editor: Amitabh Narain.
J. Heat Transfer. Feb 2018, 140(2): 021501 (10 pages)
Published Online: August 29, 2017
Article history
Received:
September 26, 2016
Revised:
June 15, 2017
Citation
Khan, A. R., Erkan, N., and Okamoto, K. (August 29, 2017). "An Experimental Study on Flow Boiling Heat Transfer From a Downward-Facing Finned Surface and Its Effect on Critical Heat Flux." ASME. J. Heat Transfer. February 2018; 140(2): 021501. https://doi.org/10.1115/1.4037154
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