Critical heat flux and pressure drop tests with high pressure water in a bundle of 0. 571- and 0. 526-inch diameter rods with a nonuniform radial and axial heat flux distribution. LWBR development program. [LWBR]

Technical Report · Wed Sep 01 04:00:00 EDT 1976

OSTI ID:7138396

Marinkovich, P S; Coeling, K J

Critical heat flux and pressure drop data were obtained for a vertical upflow of water parallel with a 24-rod bundle. Twelve rods were of 0.571-inch diameter and 12 were of 0.526-inch diameter. Both rod types were arranged on a 0.631-inch triangular pitch with half-hexagon grids used to support the rod bundle at seven axial locations. The heated length of the rods varied across the bundle from 42 inches to 84 inches. The heat flux varied both axially and radially across the bundle in a nonseparable manner. Data were taken at 520/sup 0/F and 580/sup 0/F inlet temperatures, 2000 psi system pressures, and mass velocities from 0.5 x 10/sup 6/ lb/hr-ft/sup 2/ to 1.5 x 10/sup 6/ lb/hr-ft/sup 2/. All 24 rods were not heated for each run because of rod failures. Consequently, data were obtained for 24, 23, and 22 heated rods.

• Research Organization: Bettis Atomic Power Lab., West Mifflin, Pa. (USA)
• OSTI ID: 7138396
• Report Number(s): WAPD-TM-1162
• Country of Publication: United States
• Language: English

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