Sodium-heated evaporator critical heat flux experiments at subcritical pressure conditions for commercial LMFBR plant application
Description
An experimental program was performed to investigate critical heat flux at subcritical pressure conditions in a single duplex tube sodium heated steam generator mode. The experimental ranges were: pressure: 8.274 to 12.41 MPa (1200 to 1800 psia); mass flux: 2.01*10$sup 6$ to 7.82*10$sup 6$ kg/hr-m$sup 2$ (0.43 to 1.65*10$sup 6$ lb/hr-ft$sup 2$); and heat flux: 0.48 to 0.85 MW/m$sup 2$(0.152 to 0.27*10$sup 6$ Btu/hr-ft$sup 2$). The present test data was correlated and compared with that of other investigations in terms of critical steam quality, heat flux, tube diameter, pressure, and water/steam mass flux. The resulting correlation agrees well with other sodium-heated and electrically heated test results in the range of pressure: 6.9 to 15.4 MPa (1000 to 2670 psia) and mass flux: 2.01*10$sup 6$ to 7.82*10$sup 6$ kg/hr-m$sup 2$ (0.43 to 1.65*10$sup 6$ lb/hr-ft$sup 2$). 17 refs
Additional details
Publishing Information
- Journal Title
- Am. Soc. Mech. Eng., [Pap.]
- Journal Issue
- 76-jpgc-ne-10
- Series
- Am. Soc. Mech. Eng., [Pap.].
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 8322357
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Descriptors DEI
- COMPARATIVE EVALUATIONS; CORRELATIONS; CRITICAL HEAT FLUX; DEPARTURE NUCLEATE BOILING; EVAPORATORS; LMFBR TYPE REACTORS; PRESSURE DEPENDENCE; SODIUM; STEAM GENERATORS; TUBES
- Descriptors DEC
- ALKALI METALS; BOILERS; BOILING; BREEDER REACTORS; ELEMENTS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; HEAT FLUX; LIQUID METAL COOLED REACTORS; METALS; NUCLEATE BOILING; PHASE TRANSFORMATIONS; REACTORS; VAPOR GENERATORS