A new critical heat flux correlation for vertical water flow through multiple thin rectangular channels |
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| Authors: | C.T. Wright J.E. O’Brien R.E. Spall |
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| Affiliation: | 1. Idaho National Laboratory, Idaho Falls, ID 83415, USA;2. Department of Mechanical and Aerospace Engineering, Utah State University, Logan, UT 84322, USA;1. Korea Advanced Institute of Science and Technology, 373-1 Guseong-dong, Yuseong-gu, Daejeon 305-701, Republic of Korea;2. Kyungpook National University, 80 Daehak-ro, Buk-gu, Daegu 702-701, Republic of Korea;3. Korea Atomic Energy Research Institute, 1045 Daeduk-Daero, Dukjin-Dong, Yuseong-Gu, Daejeon 305-353, Republic of Korea;4. Handong Global University, Heunghae-eup, Buk-gu, Pohang, Gyeongbuk 791-708, Republic of Korea;5. Pusan National University, 63-gil, Busandaehak-ro, Geumjeong-gu, Busan 607-735, Republic of Korea;1. Severe Accident and PHWR Safety Research Division, Korea Atomic Energy Research Institute, 989-111 Daedeok-daero, Yuseong-gu, Daejeon 305-353, Republic of Korea;2. Department of Nuclear Engineering, Seoul National University, 1 Gwanak-ro, Gwanak-gu, Seoul 151-744, Republic of Korea;1. Department of Nuclear Engineering and Radiation Health Physics, Oregon State University, 3451 SW Jefferson Way, Corvallis, OR 97331, USA;2. Department of Engineering Physics, University of Wisconsin, 1415 Engineering Drive, Madison, WI 53706, USA;1. Nuclear Safety and Thermal Power Standardization Institute, North China Electric Power University, Changping District, Beijing 102206, China;2. CNNC Key Laboratory on Nuclear Reactor Thermal Hydraulics Technology, Chengdu 610041, Sichuan Province, China |
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| Abstract: | A critical heat flux (CHF) study of the vertical up-flow of water through multiple thin rectangular channels was conducted. Pressures varied from 89.8 to 115 kPa, inlet temperatures from 291 to 306 K, and mass fluxes from 9.5 to 39 kg m?2 s?1. Electrical resistance heaters embedded in aluminum provided a uniform heat flux. A more universal and robust CHF correlation based on the geometry of the Advanced Test Reactor at Idaho National Laboratory was developed. This new CHF correlation predicts 126 data points from this and three previous studies within an error of ±8.5% with a 95% confidence. |
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