Experimental Investigation of the CHF for the Narrow Rectangular Channel in the Downward Flow
![]() |
Kim, Hui Yung
(School of Mechanical Engineering, Pusan National University)
Yun, Byong Jo (School of Mechanical Engineering, Pusan National University) Bak, Jin Yeong (School of Mechanical Engineering, Pusan National University) Park, Jong Hark (Korea Atomic Energy Research Institute(KAERI)) Chae, Heetaek (Korea Atomic Energy Research Institute(KAERI)) Park, Cheol (Korea Atomic Energy Research Institute(KAERI)) |
1 | Kaminaga, M., Yamamoto, K., and Sudo, Y., "Improvement of critical heat flux correlation for research reactors using plate-type fuel.", Journal of Nuclear Science and Technology, 1998, 35.12, 943-951. DOI |
2 | Mishima, K., "Boiling burnout at low flow rate and low pressure conditions.", Dissertation Thesis, Kyoto Univ., 1984. |
3 | Mishima, K., et al. "CHF correlations related to the core cooling of a research reactor", Proc. Int. Mtg on Reduced Enrichment for Research and Test Reactors, 1984. |
4 | Kureta, M., and H. Akimoto. "Critical heat flux correlation for subcooled boiling flow in narrow channels." International journal of heat and mass transfer, 2002, 45.20, 4107-4115. DOI |
5 | Hall, David D., and Issam Mudawar. "Critical heat flux (CHF) for water flow in tubes-II.: Subcooled CHF correlations." International Journal of Heat and Mass Transfer, 2000, 43.14, 2605-2640. DOI |
6 | Groeneveld, D. C., et al. "The 2006 CHF look-up table." Nuclear Engineering and Design, 2007, 237.15, 1909-1922. DOI |
7 | Mishima Kaichiro, and Hideaki Nishihara. "Effect of channel geometry on critical heat flux for low pressure water." International journal of heat and mass transfer, 1987, 30.6, 1169-1182. DOI |
8 | Sudo, Y., et al. "Experimental study of differences in DNB heat flux between upflow and downflow in vertical rectangular channel.", Journal of Nuclear Science and Technology, 1985, 22.8, 604-618. DOI |
9 | Sudo, Y., and Kaminaga, M., "A new CHF correlation scheme proposed for vertical rectangular channels heated from both sides in nuclear research reactors.", Journal of heat transfer, 1993, 115.2, 426-434. DOI |
![]() |