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PATHFINDER ATOMIC POWER PLANT. SUPERHEATED STEAM HEAT TRANSFER AND PRESSURE DROP EXPERIMENTS

Technical Report ·
OSTI ID:4686455
Heat transfer and pressure drop in a Pathfinder nuclear superheater fuel element is studied by simulating tests in a long, thin annular passage, which is heated both internally and externally, spaced with longitudinal spacers. Heineman's correlation of Nusselt number L/D/sub e/> 60 appears to be appropriate for superheated steam in a thin annulus with both walls heated. The friction factors are satisfactorily described by the smooth Moody curve if film temperature properties are used. Measured film coefficients are about the same on the inner and outer walls. The L/D/sub e/ effect is negligible for large values. It is shown that annular geometry with longitudinal wire spacers is amenable to treatment with the equivalent diameter concept. (N.W.R.)
Research Organization:
Allis-Chalmers Mfg. Co. Atomic Energy Div., Milwaukee
NSA Number:
NSA-17-028522
OSTI ID:
4686455
Report Number(s):
ACNP-62030
Country of Publication:
United States
Language:
English

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