A nucleate boiling heat transfer correlation for research reactors using plate-type fuel
Although bubble formation is not usually permitted in plate-type research reactor cores under normal operation, the heat flux, which leads to onset of nucleate boiling (ONB) ({alpha}{sub ONB}) in the hot channel, and the local wall superheat ({Delta}T{sub SAT}) under fully developed nucleate boiling (FDNB) need to be known in analyzing the core response to reactivity or flow excursions. Recent experiments show that q{sub ONB} may be largely over- or underestimated if the average channel flow velocity v and channel gap size d are not considered in quantifying q{sub ONB} for low-velocity, upward flows in thin, rectangular channels. These flow conditions are relevant to plate-type research reactors following coolant pump trip or when ore cooling under normal operation is by natural convection. The experiments also show that {Delta}T{sub sat} is independent of v in the FDNB regime. This paper investigates the effect of d on {Delta}T{sub sat} in FDNB for upward flows in 2{le}d{le}4-mm rectangular channels, compares the experimental data to predictions by some currently available correlations, and proposes a new correlation to determine {Delta}T{sub sat} within the local pressure p range of 1.36 to 1.48 atm.
- OSTI ID:
- 7028406
- Report Number(s):
- CONF-890604-; CODEN: TANSA; TRN: 90-023520
- Journal Information:
- Transactions of the American Nuclear Society; (USA), Vol. 59; Conference: Annual meeting of the American Nuclear Society, Atlanta, GA (USA), 4-8 Jun 1989; ISSN 0003-018X
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
42 ENGINEERING
REACTOR CHANNELS
NUCLEATE BOILING
RESEARCH REACTORS
BUBBLES
DATA COVARIANCES
ERRORS
FLOW RATE
FLOW VISUALIZATION
FUEL PLATES
HEAT FLUX
HEAT TRANSFER
HYDRAULICS
NATURAL CONVECTION
PUMPS
REACTOR COOLING SYSTEMS
REACTOR CORES
REACTOR OPERATION
TWO-PHASE FLOW
BOILING
CONVECTION
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
FLUID FLOW
FLUID MECHANICS
FUEL ELEMENTS
MASS TRANSFER
MECHANICS
OPERATION
PHASE TRANSFORMATIONS
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
220600* - Nuclear Reactor Technology- Research
Test & Experimental Reactors
420400 - Engineering- Heat Transfer & Fluid Flow