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Title: Critical heat flux experiments in a heated rod bundle with upward crossflow of Freon 114

Technical Report ·
DOI:https://doi.org/10.2172/319773· OSTI ID:319773

Critical heat flux (CHF) data were obtained for upward crossflow of R-114 in a heated staggered rod bundle. Data were obtained over a broad range of mass fluxes (135 to 1,221 kg/m{sup 2} sec), inlet subcooling (0 to 55 C), and qualities ({minus}0.42 to 0.92). The present work extends the available database to higher quality, inlet subcooling, and mass flux. The test section is 3.43 cm x 15.24 cm (1.35 in. x 6 in.) in cross section with a total length of 55.88 cm (22 inches) from the top of the inlet flow straightener to the perforated plate at the test section exit. The rod bundle has a triangular pitch with a diameter (D) of 0.635 cm (0.25 in), and a pitch to diameter (P/D) ratio of 1.5. The rod bundle has 165 rods with a 15.24 cm (6 in.) heated length arranged in 55 rows of three rods each. Unheated half rods were positioned on the walls of the test section to maintain the regular rod arrangement and prevent flow bypass along the gaps between the window and the first column of heated rods. A single instrumented heater was positioned five rows upstream from the bundle exit to determine CHF. The last three rows of rods in the bundle were unheated to prevent undetected dryout downstream of the CHF position. Temperature excursions due to CHF were sensed using four imbedded thermocouples (TC) in the heater rod. The four TC temperatures were continuously monitored on a strip chart recorder. The rod heat was gradually increased until CHF was detected. Overall, the data are in good agreement with the Jensen and Tang correlation in the range of application of this correlation. The local minima in CHF which occurs near zero quality is slightly lower in the present experiment than for the Jensen and Tang correlation. At high quality, CHF drops off more rapidly than the Jensen-Tang prediction. Data are now available to extend the existing correlations to higher quality, and higher inlet subcooling.

Research Organization:
Knolls Atomic Power Lab. (KAPL), Niskayuna, NY (United States)
Sponsoring Organization:
USDOE Assistant Secretary for Nuclear Energy, Washington, DC (United States)
DOE Contract Number:
AC12-76SN00052
OSTI ID:
319773
Report Number(s):
KAPL-P-000143; K-97003; CONF-970824-; ON: DE99001880; TRN: 99:003948
Resource Relation:
Conference: AICHE/ASME national heat transfer conference: current developments in numerical simulation of heat and mass transfer, Baltimore, MD (United States), 10-12 Aug 1997; Other Information: PBD: Feb 1997
Country of Publication:
United States
Language:
English