Experimental and computational investigations of heat and mass transfer of intensifier grids
- 1. Nuclear Research Centre ''Kurchatov Institute'', Moscow (Russian Federation)
Description
The paper discusses experimental and numerical investigations on intensification of thermal and mass exchange which were performed by National Research Centre ''Kurchatov Institute'' over the past years. Recently, many designs of heat mass transfer intensifier grids have been proposed. NRC ''Kurchatov Institute'' has accomplished a large scope of experimental investigations to study efficiency of intensifier grids of various types. The outcomes of experimental investigations can be used in verification of computational models and codes. On the basis of experimental data, we derived correlations to calculate coolant mixing and critical heat flux mixing in rod bundles equipped with intensifier grids. The acquired correlations were integrated in subchannel code SC-INT.
Additional details
Publishing Information
- Journal Title
- Kerntechnik (1987)
- Journal Volume
- 80
- Journal Issue
- 4
- Journal Page Range
- p. 349-358
- ISSN
- 0932-3902
- CODEN
- KERNEU
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 46116733
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- CONVECTION; COOLANTS; COOLING; CORRELATIONS; CRITICAL HEAT FLUX; FUEL ELEMENT CLUSTERS; FUEL RODS; MIXING; PRESSURE RANGE MEGA PA 10-100; REACTOR COOLING SYSTEMS; S CODES; TEMPERATURE RANGE 0400-1000 K; TURBULENT FLOW; WWER TYPE REACTORS
- Descriptors DEC
- COMPUTER CODES; COOLING SYSTEMS; ENERGY SYSTEMS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FLUID FLOW; FUEL ASSEMBLIES; FUEL ELEMENTS; HEAT FLUX; HEAT TRANSFER; MASS TRANSFER; POWER REACTORS; PRESSURE RANGE; PRESSURE RANGE MEGA PA; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTORS; TEMPERATURE RANGE; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS