Reflooding heat transfer in zirconium alloy rod bundles of the VVER reactor
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5986012
Heat transfer experimental research in seven-rod bundles of Zr + 1% Nb alloy has been carried out at different kinds of water injections: bottom, top, and combined. The rod bundle characteristics are defined, and the range of experimental parameters chosen are described. The results of current experimental research are several empirical correlations for calculations of rewetting velocity, heat transfer coefficient downstream of quench front and heat transfer enhancement due to grid spacers at the bottom reflooding conditions.
- OSTI ID:
- 5986012
- Report Number(s):
- CONF-881011-
- Journal Information:
- Trans. Am. Nucl. Soc.; (United States), Journal Name: Trans. Am. Nucl. Soc.; (United States) Vol. 57; ISSN TANSA
- Country of Publication:
- United States
- Language:
- English
Similar Records
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Journal Article
·
Fri Nov 30 23:00:00 EST 1979
· Nucl. Technol.; (United States)
·
OSTI ID:5533003
Reflood heat transfer in the FLECHT-SEASET 163-rod bundle with flow blockage and bypass
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Mon Oct 31 23:00:00 EST 1983
· Am. Soc. Mech. Eng., (Pap.); (United States)
·
OSTI ID:6930587
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Conference
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Sat Jul 01 00:00:00 EDT 2006
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OSTI ID:20997061
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Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
42 ENGINEERING
420400 -- Engineering-- Heat Transfer & Fluid Flow
ACCIDENTS
ACCURACY
ALLOYS
COOLING
DIMENSIONS
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
FLUID MECHANICS
HEAT FLUX
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
MATHEMATICAL MODELS
MECHANICS
NIOBIUM ADDITIONS
NIOBIUM ALLOYS
PRESSURE DEPENDENCE
PWR TYPE REACTORS
QUENCHING
REACTOR ACCIDENTS
REACTOR SAFETY
REACTOR SAFETY EXPERIMENTS
REACTORS
ROD BUNDLES
SAFETY
SPACERS
SUBCOOLING
TEMPERATURE DEPENDENCE
THERMAL REACTORS
VELOCITY
WATER COOLED REACTORS
WATER MODERATED REACTORS
WWER TYPE REACTORS
ZIRCONIUM ALLOYS