Subchannel analysis and correlation of the Rod Bundle Heat Transfer (RBHT) steam cooling experimental data

Kerntechnik ◽  
2016 ◽  
Vol 81 (3) ◽  
pp. 214-220 ◽  
Author(s):  
M. P. Riley ◽  
L. Mohanta ◽  
D. J. Miller ◽  
F. B. Cheung ◽  
S. M. Bajorek ◽  
...  
Keyword(s):  
Heat Transfer ◽  
Experimental Data ◽  
Rod Bundle ◽  
Steam Cooling ◽  
Subchannel Analysis

Experimental Study of Heat Transfer to Supercritical Pressure Water Flowing in a 2×2 Rod Bundle

2014 ◽  
Author(s):  
Han Wang ◽  
Qincheng Bi ◽  
Linchuan Wang ◽  
Haicai Lv ◽  
Laurence K. H. Leung
Keyword(s):  
Heat Transfer ◽  
Experimental Data ◽  
Heat Flux ◽  
Pressure Drop ◽  
Wall Temperature ◽  
Mass Flux ◽  
Heat Fluxes ◽  
Outer Diameter ◽  
Square Channel ◽  
Rod Bundle

An experiment has recently been performed at Xi’an Jiaotong University to study the wall temperature and pressure drop at supercritical pressures with upward flow of water inside a 2×2 rod bundle. A fuel-assembly simulator with four heated rods was installed inside a square channel with rounded corner. The outer diameter of each heated rod is 8 mm with an effective heated length of 600 mm. Experimental parameters covered the pressure of 23–28 MPa, mass flux of 350–1000 kg/m2s and heat flux on the rod surface of 200–1000 kW/m2. According to the experimental data, it was found that the circumferential wall temperature distribution of a heated rod is not uniform. The temperature difference between the maximum and the minimum varies with heat flux and/or mass flux. Heat transfer characteristics of supercritical water in bundle were discussed with respect to various heat fluxes. The effect of heat flux on heat transfer in rod bundles is similar with that in tubes or annuli. In addition, flow resistance reflected in the form of pressure loss has also been studied. Experimental results showed that the total pressure drop increases with bulk enthalpy and mass flux. Four heat transfer correlations developed for supercritical pressures water were compared with the present test data. Predictions of Jackson correlation agrees closely with the experimental data.

scholarly journals ORNL rod-bundle heat-transfer test data. Volume 4. ORNL small-break LOCA heat transfer test series II: experimental data report. [PWR]

1982 ◽  
Author(s):  
T. M. Anklam ◽  
D. F. Hunt ◽  
D. K. Felde ◽  
M. S. Thompson ◽  
A. G. Sutton ◽  
...  
Keyword(s):  
Heat Transfer ◽  
Experimental Data ◽  
Test Data ◽  
Transfer Test ◽  
Test Series ◽  
Rod Bundle ◽  
Data Volume

Rod Bundle Heat Transfer: Steady-State Steam Cooling Experiments

2006 ◽  
Author(s):  
J. P. Spring ◽  
D. M. McLaughlin
Keyword(s):  
Heat Transfer ◽  
Heat Flux ◽  
Reynolds Number ◽  
Heat Transfer Enhancement ◽  
Local Heat Transfer ◽  
Local Heat ◽  
Transfer Enhancement ◽  
Spacer Grids ◽  
Rod Bundle ◽  
Steam Cooling

Through the joint efforts of the Pennsylvania State University and the United States Nuclear Regulatory Commission, an experimental rod bundle heat transfer (RBHT) facility was designed and built. The rod bundle consists of a 7×7 square pitch array with spacer grids and geometry similar to that found in a modern pressurized water reactor. From this facility, a series of steady-state steam cooling experiments were performed. The bundle inlet Reynolds number was varied from 1 400 to 30 000 over a pressure range from 1.36 to 4 bars (20 to 60 psia). The bundle inlet steam temperature was controlled to be at saturation for the specified pressure and the fluid exit temperature exceeded 550 °C in the highest power tests. One important quantity of interest is the local convective heat transfer coefficient defined in terms of the local bulk mean temperature of the flow, local wall temperature, and heat flux. Steam temperatures were measured at the center of selected subchannels along the length of the bundle by traversing miniaturized thermocouples. Using an analogy between momentum and energy transport, a method was developed for relating the local subchannel centerline temperature measurement to the local bulk mean temperature. Wall temperatures were measured using internal thermocouples strategically placed along the length of each rod and the local wall heat flux was obtained from an inverse conduction program. The local heat transfer coefficient was calculated from the data at each rod thermocouple location. The local heat transfer coefficients calculated for locations where the flow was fully developed were compared against several published correlations. The Weisman and El-Genk correlations were found to agree best with the RBHT steam cooling data, especially over the range of turbulent Reynolds numbers. The effect of spacer grids on the heat transfer enhancement was also determined from instrumentation placed downstream of the spacer grid locations. The local heat transfer was found to be greatest at locations immediately downstream of the grid, and as the flow moved further downstream from the grid it became more developed, thus causing the heat transfer to diminish. The amount of heat transfer enhancement was found to depend not only on the spacer grid design, but also on the local Reynolds number. It was seen that decreasing Reynolds number leads to greater heat transfer enhancement.

scholarly journals ORNL rod bundle heat transfer test data. Volume 1. ORNL small break LOCA test series: experimental data report. [PWR]

1982 ◽  
Author(s):  
T. M. Anklam ◽  
D. F. Hunt ◽  
M. S. Thompson ◽  
D. K. Felde ◽  
A. Sutton ◽  
...  
Keyword(s):  
Heat Transfer ◽  
Experimental Data ◽  
Test Data ◽  
Transfer Test ◽  
Test Series ◽  
Rod Bundle ◽  
Data Volume
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