Departure from nucleate boiling in annular flow channels calculated by the Weisman physically-based DNB (departure from nucleate boiling) correlation
Conference
·
OSTI ID:7242919
Departure from nucleate boiling (DNB) correlations have historically been empirical relationships used to interpolate and smooth measured data. The correlations generally used a number of fitted parameters and had limited reliability for extrapolation. In this paper, a phenomenological DNB correlation for the forced convection, subcooled, and low-quality region is used to correlate subchannel DNB measurements for tube and annuli to improve the understanding of the trends in the DNB phenomena and to reduce the effect of individual outlying measurements. Other advantages of the phenomenological method, besides reducing the number of fitted parameters to one, were to reduce the standard deviation of measured data about the DNB correlation prediction and to have a basis for filling in gaps in the previously measured data. By this approach, the DNB correlation has served to improve the implementation of DNB measurements for their intended purpose.
- Research Organization:
- Westinghouse Hanford Co., Richland, WA (USA)
- DOE Contract Number:
- AC06-87RL10930
- OSTI ID:
- 7242919
- Report Number(s):
- WHC-SA-0159-FP; CONF-880724-18; ON: DE88009196
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210300* -- Power Reactors
Nonbreeding
Graphite Moderated
42 ENGINEERING
420400 -- Engineering-- Heat Transfer & Fluid Flow
BOILING
CORRELATION FUNCTIONS
CORRELATIONS
DATA
DEPARTURE NUCLEATE BOILING
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
FLOW RATE
FLUID MECHANICS
FUNCTIONS
GRAPHITE MODERATED REACTORS
HEAT FLOW
HEAT TRANSFER
HYDRAULICS
INFORMATION
LWGR TYPE REACTORS
MATHEMATICAL MODELS
MECHANICS
N-REACTOR
NUCLEATE BOILING
NUMERICAL DATA
PHASE TRANSFORMATIONS
PLUTONIUM PRODUCTION REACTORS
POWER REACTORS
PRODUCTION REACTORS
REACTORS
STATISTICAL DATA
SUBCOOLED BOILING
THERMODYNAMICS
WATER COOLED REACTORS
210300* -- Power Reactors
Nonbreeding
Graphite Moderated
42 ENGINEERING
420400 -- Engineering-- Heat Transfer & Fluid Flow
BOILING
CORRELATION FUNCTIONS
CORRELATIONS
DATA
DEPARTURE NUCLEATE BOILING
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
FLOW RATE
FLUID MECHANICS
FUNCTIONS
GRAPHITE MODERATED REACTORS
HEAT FLOW
HEAT TRANSFER
HYDRAULICS
INFORMATION
LWGR TYPE REACTORS
MATHEMATICAL MODELS
MECHANICS
N-REACTOR
NUCLEATE BOILING
NUMERICAL DATA
PHASE TRANSFORMATIONS
PLUTONIUM PRODUCTION REACTORS
POWER REACTORS
PRODUCTION REACTORS
REACTORS
STATISTICAL DATA
SUBCOOLED BOILING
THERMODYNAMICS
WATER COOLED REACTORS