RESULTS OF FINAL HIGH HEAT FLUX TESTS AT 2000 PSIA ON PARALLEL FLOW RODS
Technical Report
·
OSTI ID:4220163
High heat flux tests were conducted with vertical upflow of water at 2000 psia using a test section having nine heated rods (0.413 in. diameter x 0.468 in. square pitch x 9 1/4 in. long). These tests confirmed the validity of using the present Bettis design procedure based on tests with rectangular channels, for calculating DNB heat flux for parallel flow through heated rod bundles. The tests were run with mass velocities from 0.25 to 1.0 x 10/sup 6/ lb/ hr-ft/sup 2/, at inlet temperatures from 400 to 625 deg F. Although because of instrumentation difficulties only 2 actual meltdown points were obtained it was still shown that in the range of variables covered the use of the DNB design equation for rectangular channels will yield conservative values of DNB heat fluxes for flow outside of parallel rod bundles. The results represent the completed DNB program for parallel flow through PWR type rod bundles. (auth)
- Research Organization:
- Westinghouse Electric Corp. Atomic Power Div., Pittsburgh
- NSA Number:
- NSA-14-000284
- OSTI ID:
- 4220163
- Report Number(s):
- WAPD-TH-478
- Country of Publication:
- United States
- Language:
- English
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