CHF experiments were conducted in subcooled flow boiling region at atmospheric pressure. Magnetite nanoparticles were deposited sufficiently on the test sections in same deposition process. Then, working fluid was changed to DI water. After the nanoparticle deposition process, the surface became very hydrophilic even after CHF experiment using DI water. The wettable surfaces were observed using static contact angle and SEM image. CHF results of bare stainless surface and nanoparticle-deposited surface were obtained in the subcooled boiling region. Experiments were conducted over a mass flux range from 1,000 kg/m2s to 5,000 kg/m2s and with inlet temperatures of 40, 60, and 80 °C. The CHF enhancement was from 0% to 40 % by the nanoparticle deposition, which is related wettability enhancement. The CHF enhancement increased as the mass flux increased, which lead to exit quality decrement.
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2017 25th International Conference on Nuclear Engineering
July 2–6, 2017
Shanghai, China
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5784-7
PROCEEDINGS PAPER
Experiment of CHF Enhancement by Magnetite Nanoparticle Deposition in the Subcooled Flow Boiling Region Available to Purchase
Young Jae Choi,
Young Jae Choi
Korea Advanced Institute of Science and Technology, Yuseong-gu, Republic of Korea
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Dong Hoon Kam,
Dong Hoon Kam
Korea Advanced Institute of Science and Technology, Yuseong-gu, Republic of Korea
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Yong Hoon Jeong
Yong Hoon Jeong
Korea Advanced Institute of Science and Technology, Yuseong-gu, Republic of Korea
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Young Jae Choi
Korea Advanced Institute of Science and Technology, Yuseong-gu, Republic of Korea
Dong Hoon Kam
Korea Advanced Institute of Science and Technology, Yuseong-gu, Republic of Korea
Yong Hoon Jeong
Korea Advanced Institute of Science and Technology, Yuseong-gu, Republic of Korea
Paper No:
ICONE25-67087, V006T08A077; 9 pages
Published Online:
October 17, 2017
Citation
Choi, YJ, Kam, DH, & Jeong, YH. "Experiment of CHF Enhancement by Magnetite Nanoparticle Deposition in the Subcooled Flow Boiling Region." Proceedings of the 2017 25th International Conference on Nuclear Engineering. Volume 6: Thermal-Hydraulics. Shanghai, China. July 2–6, 2017. V006T08A077. ASME. https://doi.org/10.1115/ICONE25-67087
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