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uclear power technology in the thermal-hydraulic Note 1: all kinds of pressure drop calculation method is the use of presentation 1) Todreas group Low-pressure system Air - liquid mixture Lockhart-Marttinelli High-pressure water p> 200psia lbm / (h · ft 5 0.5 10 G> × 2 ) Thom (Marttinelli-Nelson) General relationship That liquid metal Baroczy Analytical expression High gas rate, high pressure High flow rate, simple Uniform flow 2) The following article the author or organization: ESDU, 1977; IDSINGU, 1973; FRIEDEL, 1976; BRYCE, 1977; WHALLEY, 1980; EPRI (Electric Power Research Institute), TR-113189, "drop design and analysis methods," August 1999. 3) WHALLE Y of recommendation (from Collier and Thome68 pages)

NUclear Power Technology in the Thermal

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Page 1: NUclear Power Technology in the Thermal

uclear power technology in the thermal-hydraulicNote 1: all kinds of pressure drop calculation method is the use of presentation1) Todreas groupLow-pressure systemAir - liquid mixtureLockhart-MarttinelliHigh-pressure waterp> 200psialbm / (h · ft50.5 10G>×2)Thom (Marttinelli-Nelson)General relationshipThat liquid metalBaroczyAnalytical expressionHigh gas rate, high pressureHigh flow rate, simpleUniform flow2) The following article the author or organization:ESDU, 1977;IDSINGU, 1973;FRIEDEL, 1976;BRYCE, 1977;WHALLEY, 1980;EPRI (Electric Power Research Institute), TR-113189, "drop design and analysis methods," August 1999.3) WHALLE Y of recommendation (from Collier and Thome68 pages)WHALLE Y (1980) evaluated the separation with large amounts of data flow model, we recommend the following relationship:For/1000:fgμμ

Page 2: NUclear Power Technology in the Thermal

<(1979) relationship with FRIEDEL;For/1000G100:fgμμ>>AndWith the recent improvement of Chisholm (1973) relationship;For/1000G <100:fgμμ>AndWith Lockhart-Marttinelli (1949) Relations andMarttinelli-Nelson (1948) relationship.For most fluid and operating conditions,/fgμμ1,000 or less, preferred FRIEDEL relationship.1/2

Page 222.313Nuclear power technology in the thermal-hydraulicReferences:ESDU (1977), "The gravitational component of pressure gradient for two-phase gasor vapor / liquid flow through straight pipes "Engineering Science Data Unit, London

Page 3: NUclear Power Technology in the Thermal

Idsinga, W. (1975), "An assessment of two-phase pressure drop correlations for steam-watersystems ", MsC Thesis, MIT - Department of Nuclear Engineering, May.Friedel, L. (1975), "Momentum exchange and pressure drop in two-phase", proceedings NATOAdvanced Study Institute, Istanbul, Turkey, 16-27 August, I, 239-312. Hemisphere Pub. Corp.(Also see Appendix B, P. Whalley "Boiling Condensation and Gas-Liquid Flow", Oxford, 1987).Bryce, WM (1977), "A new flow dependent slip correlation which gives hyperbolic steam-watermixture flow equation ", AEEW-R 1099.Whalley, PB (1980), Private Communication to GF Hewitt

CHF:Ishii,shah,martinel,bowring john c chen, merilo, bjornard, berglez, tong, groevneld,