BURNOUT CONDITIONS FOR SINGLE ROD IN ANNULAR GEOMETRY, WATER AT 600 TO 1400 PSIA
Tests were run to determine burnout conditions for sn electrically heated rod in a circular tube with an annular flow path for the upward water flow. The conditions correspond to those which might exist in a reactor core. The burnout results for the basic test geometry (straight concentric annulus) showed that a plot of burnout heat flux vs quality is a straight line with a negative slope, and that the burnout heat flux is increased by a decrease in flow or an increase in pressure, while the hydraulic diameter has a maximum effect on the flux at 0.25 to 0.5 inch. A correlation of the results is given for a certain range of conditions. The following modifications of the basic test geometry were also tested: eccentric rod, simulated spacer, sandblasted rod, and rough liner. The eccentric rod and sandblasted rod decreased the burnout heat flux, while the simulated space had no effect, and the flux for the rough liner is greater than for the smooth liner. The basic test geometry data are compared with other internally heated annular data and with multirod data. (D.L.C.)
- Research Organization:
- General Electric Co. Atomic Power Equipment Dept., San Jose, Calif.
- NSA Number:
- NSA-18-005464
- OSTI ID:
- 4136515
- Report Number(s):
- GEAP-3899
- Country of Publication:
- United States
- Language:
- English
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