Effect of spacer grids on post-CHF rod bundle heat transfer
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:6762411
None
- Research Organization:
- ORNL, Oak Ridge, TN 37830
- OSTI ID:
- 6762411
- Report Number(s):
- CONF-811103-
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 39
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220300* -- Nuclear Reactor Technology-- Fuel Elements
42 ENGINEERING
420400 -- Engineering-- Heat Transfer & Fluid Flow
CRITICAL HEAT FLUX
ENERGY TRANSFER
FLUID FLOW
FLUID MECHANICS
HEAT FLUX
HEAT TRANSFER
MEASURING INSTRUMENTS
MEASURING METHODS
MECHANICS
PWR TYPE REACTORS
REACTORS
ROD BUNDLES
THERMOCOUPLES
WATER COOLED REACTORS
WATER MODERATED REACTORS
220300* -- Nuclear Reactor Technology-- Fuel Elements
42 ENGINEERING
420400 -- Engineering-- Heat Transfer & Fluid Flow
CRITICAL HEAT FLUX
ENERGY TRANSFER
FLUID FLOW
FLUID MECHANICS
HEAT FLUX
HEAT TRANSFER
MEASURING INSTRUMENTS
MEASURING METHODS
MECHANICS
PWR TYPE REACTORS
REACTORS
ROD BUNDLES
THERMOCOUPLES
WATER COOLED REACTORS
WATER MODERATED REACTORS