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Journal of Nuclear Science and Technology Volume 44, 2007 - Issue 9
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ARTICLE

Critical Heat Flux in a Heater Rod Bundle Cooled by R-134a Fluid near the Critical Pressure

Se-Young CHUN Korea Atomic Energy Research Institute, 150 Deokjin-dong, Yuseong-gu, Daejeon, 305-353, Republic of Korea
,
Sung-Deok HONG Korea Atomic Energy Research Institute, 150 Deokjin-dong, Yuseong-gu, Daejeon, 305-353, Republic of Korea
,
Hiroshige KIKURA Tokyo Institute of Technology, 2-12-1 Ohokayama, Meguro-ku, Tokyo, 152-8550, Japan
&
Masanori ARITOMI Tokyo Institute of Technology, 2-12-1 Ohokayama, Meguro-ku, Tokyo, 152-8550, Japan
Pages 1189-1198 | Received 21 Dec 2006, Accepted 06 Jun 2007, Published online: 05 Jan 2012

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Hyun-Sik Park, Hwang Bae, Sung-Uk Ryu, Byong-Guk Jeon, Jin-Hwa Yang, Sung-Jae Yi & Young-Jong Chung. (2023) Thermal-Hydraulic Research Supporting the Development of SMART. Nuclear Technology 209:10, pages 1617-1635.
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Articles from other publishers (7)

Kathleen Lyons, Donghwi Lee & Mark Anderson. (2020) Experimental study for critical heat flux in 2x2 rod bundles at high pressure conditions. Nuclear Engineering and Design 365, pages 110730.
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Sihui Hong, Yongle Tang & Shuangfeng Wang. (2018) Investigation on critical heat flux of flow boiling in parallel microchannels with large aspect ratio: Experimental and theoretical analysis. International Journal of Heat and Mass Transfer 127, pages 55-66.
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Yuzhou Chen, Minfu Zhao, Keming Bi, Bin Yang, Dongxu Zhang & Kaiwen Du. (2018) Critical Heat Flux of Flowing Water in Tube for Pressure Up to Near Critical Point—Experiment and Prediction. Journal of Nuclear Engineering and Radiation Science 4:1.
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Hyun-Sik Park, Tae-Soon Kwon, Sang-Ki Moon, Seok Cho, Dong-Jin Euh & Sung-Jae Yi. (2017) Contribution of thermal–hydraulic validation tests to the standard design approval of SMART. Nuclear Engineering and Technology 49:7, pages 1537-1546.
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Ahmad Eter, Dé Groeneveld & Stavros Tavoularis. (2017) Convective heat transfer at high subcritical pressures in tubes with and without flow obstacles. Nuclear Engineering and Design 318, pages 1-23.
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Luzhi Tan, Changnian Chen, Xiaoming Dong, Zhiqiang Gong & Mingtao Wang. (2017) Experimental study on CHF of R134a flow boiling in a horizontal helically-coiled tube near the critical pressure. Experimental Thermal and Fluid Science 82, pages 472-481.
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Takashi MAWATARI & Hideo MORI. (2016) An experimental study on characteristics of post-CHF heat transfer in the high subcritical pressure region near to the critical pressure. Journal of Thermal Science and Technology 11:1, pages JTST0006-JTST0006.
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