Heat removal characteristics of volume-heated boiling pools with inclined boundaries in bubbly flow regime
Conference
·
OSTI ID:6258475
The heat transfer characteristics of volume-heated boiling pools are of importance in the safety analysis of hypothetical core disruptive accidents in liquid metal fast breeder reactors. Investigations into the heat transfer and hydrodynamic behavior of such volume-heated boiling pools have been few. The existing work in boiling pool heat transfer is reviewed, and current modeling efforts are described. The current experiment is discussed in detail, and significant improvements in experimental techniques are described. The data for local convective boundary heat transfer coefficient and pool-averaged void fraction are presented for the bubbly flow regime over a range of dimensionless power, j/sub g/sup 00//U/sub 00/, up to unity, and wall angles of 90/sup 0/ (vertical), 75/sup 0/, and 60/sup 0/. The data are compared to existing correlations for local heat transfer and to a one-dimensional drift flux model for local and average void fraction. It is shown that the drift flux model predicted the experimental data for average void fraction in the bubbly flow regime well when based upon the net boiling power. However, it was demonstrated that the existing correlations for local and average boundary heat flux (based on Gustavson's data) underpredicted the present data by as much as a factor of 2 or more.
- Research Organization:
- Brookhaven National Lab., Upton, NY (USA)
- DOE Contract Number:
- EY-76-C-02-0016
- OSTI ID:
- 6258475
- Report Number(s):
- BNL-NUREG-26083; CONF-790808-7
- Country of Publication:
- United States
- Language:
- English
Similar Records
Correlation of local heat flux from inclined volume-heated pools in bubbly flow
Correlation of local heat flux from inclined volume-heated pools in bubbly flow
Comparison of measured and calculated average void fraction in volume-boiling pools with inclined boundaries. [LMFBR]
Conference
·
Mon Dec 31 23:00:00 EST 1979
·
OSTI ID:6278936
Correlation of local heat flux from inclined volume-heated pools in bubbly flow
Journal Article
·
Mon Dec 31 23:00:00 EST 1979
· Am. Soc. Mech. Eng., (Pap.); (United States)
·
OSTI ID:6253500
Comparison of measured and calculated average void fraction in volume-boiling pools with inclined boundaries. [LMFBR]
Conference
·
Sun Dec 31 23:00:00 EST 1978
·
OSTI ID:6069198
Related Subjects
42 ENGINEERING
420400* -- Engineering-- Heat Transfer & Fluid Flow
BOILING
BREEDER REACTORS
DATA
ENERGY TRANSFER
EPITHERMAL REACTORS
EXPERIMENTAL DATA
FAST REACTORS
FBR TYPE REACTORS
FLUID FLOW
HEAT TRANSFER
INFORMATION
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MATHEMATICAL MODELS
MEASURING METHODS
NUMERICAL DATA
PHASE TRANSFORMATIONS
POOL BOILING
REACTORS
SAFETY
TWO-PHASE FLOW
VOID FRACTION
420400* -- Engineering-- Heat Transfer & Fluid Flow
BOILING
BREEDER REACTORS
DATA
ENERGY TRANSFER
EPITHERMAL REACTORS
EXPERIMENTAL DATA
FAST REACTORS
FBR TYPE REACTORS
FLUID FLOW
HEAT TRANSFER
INFORMATION
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MATHEMATICAL MODELS
MEASURING METHODS
NUMERICAL DATA
PHASE TRANSFORMATIONS
POOL BOILING
REACTORS
SAFETY
TWO-PHASE FLOW
VOID FRACTION