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CRITICAL HEAT FLUX DATA FOR FULLY DEVELOPED FLOW OF STEAM-WATER MIXTURES IN ROUND VERTICAL TUBES. Topical Report No. 4.

Author: Bertoletti, S.
Published: [Place of publication not identified] : [publisher not identified], 1962.
[Oak Ridge, Tennessee] : [U.S. Atomic Energy Commission], 1962.
Physical Description: microfiche : negative ; 8 x 13 cm
Additional Creators: Gaspari, G. P., Lombardi, C., Peterlongo, G., Silvestri, M., Soldaini, G., and Zavattarelli, R.

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Summary

Data are presented for pressures of 71.5 kg/cm/sup 2/ abs. The tube length-to-dia. ratio range in the experiments was 3.61 at the lower limit to 295.1 at the upper limit. The analysis of these data is in progress. (J.R.D.)

Report Numbers

CISE-R-63; EURAEC-517

Other Subject(s)

Collection

U.S. Atomic Energy Commission depository collection.

Note

NSA number: NSA-17-021873
OSTI Identifier 4727561
Research organization: Centro Informazioni Studi Esperienze, Milan.

View MARC record | catkey: 39687403

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CRITICAL HEAT FLUX DATA FOR FULLY DEVELOPED FLOW OF STEAM-WATER MIXTURES IN ROUND VERTICAL TUBES. Topical Report No. 4.

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