Thermal-hydraulic analysis for fuel elements with liquid-metal cooling

Conference · Mon Jan 01 04:00:00 EST 1973

OSTI ID:4398060

Voj, P; Markfort, D; Ruppert, E; Dwyer, O E ^[1]

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1. ed.

From 4th international seminar on heat and mass transfer in liquid metals; Trojir, Yugoslavia (6 Sep 1971). See CONFAnalytical and experimental studies of the thermohydraulic behavior of a fuel rod bundle, cooled by steady- state, singlephase flow with special emphasis on liquid metals are described. Performance data on pressure drop, velocity distribution, and mixing rate of mock- up bundles are presented. Spacer grids typical of the design of the fuel subassembly of the SNR-300 are taken into account; and the result of an illustrative calculation of the temperature field in the spacer grid area is given. (auth)

• Research Organization: INTERATOM, Cologne
• NSA Number: NSA-29-000287
• OSTI ID: 4398060
• Country of Publication: Country unknown/Code not available
• Language: English

Related Subjects

*FUEL ELEMENT CLUSTERS-- THERMAL ANALYSIS
*LIQUID METAL COOLED REACTORS-- FUEL ELEMENT CLUSTERS
*LIQUID METALS-- TURBULENT FLOW
COOLING
FBR TYPE REACTORS
FLOW RATE
HYDRAULICS
LIQUID FLOW
MIXING
N42300* --Engineering--Heat Transfer & Fluid Flow
N77500 -- Reactors--Power Reactors
Breeding
NUMERICAL SOLUTION
PRESSURE GRADIENTS
TEMPERATURE DISTRIBUTION
TEMPERATURE DISTRIBUTION PRESSURE GRADIENTS