Improvement of critical heat flux correlation for research reactors using plate-type fuel

Citation
M. Kaminaga et al., Improvement of critical heat flux correlation for research reactors using plate-type fuel, J NUC SCI T, 35(12), 1998, pp. 943-951
Citations number
10
Categorie Soggetti
Nuclear Emgineering
Journal title
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY
ISSN journal
00223131 → ACNP
Volume
35
Issue
12
Year of publication
1998
Pages
943 - 951
Database
ISI
SICI code
0022-3131(199812)35:12<943:IOCHFC>2.0.ZU;2-1
Abstract
In research reactors, plate-type fuel elements are generally adopted so as to produce high power densities and are cooled by a downward flow. A core f low reversal from a steady-state forced downward flow to an upward flow due to natural convection should occur during operational transients such as " Loss of the primary coolant now". Therefore, in the thermal hydraulic desig n of research reactors, critical heat nux (CHF) under a counter-current flo w limitation (CCFL) or a flooding condition are important to determine safe ty margins of fuel against CHF during a core flow reversal. The authors have proposed a CHF correlation scheme for the thermal hydrauli c design of research reactors, based on CHF experiments for both upward and downward flows including CCFL condition. When the CHF correlation scheme w as proposed, a subcooling effect for CHF correlation under CCFL condition h ad not been considered because of a conservative evaluation and a lack of e nough CHF data to determine the subcooling effect on CHF. A too conservative evaluation is not appropriate for the design of research reactors because of construction costs etc. Also, conservativeness of the design must be determined precisely. In this study, therefore, the subcooli ng effect on CHF under the CCFL conditions in vertical rectangular channels heated from both sides were investigated quantitatively based on CHF exper imental results obtained under uniform and non-uniform heat flux conditions . As a result, it was made clear that CHF in this region increase linearly with an increase of the channel inlet subcooling and a new CHF correlation including the effect of channel inlet subcooling was proposed. The new corr elation could be adopted under the conditions of the atmospheric pressure, the inlet subcooling less than 78 K, the channel gap size between 2.25 to 5 .0 mm, the axial peaking factor between 1.0 to 1.6 and L/De between 71 to 1 74 which were the ranges investigated in this study.