Experimental study of heavy-liquid metal (LBE) flow and heat transfer along a hexagonal 19-rod bundle with wire spacers
Description
Highlights: • A unique experiment with lead–bismuth eutectic (LBE) as working fluid was performed. • Detailed temperature measurements were implemented at three axial positions. • The experimental results present a good repeatability within the uncertainties. • Pressure drop results agree with water correlations, as expected. • The Nusselt number is well predicted by the most conservative correlation. - Abstract: An experimental campaign considering a 19-pin hexagonal rod bundle with wire spacers, cooled by forced-convective LBE was completed at the Karlsruhe Liquid Metal Laboratory (KALLA). In the frame of the European research project SEARCH (Safe Exploitation Related Chemistry for HLM Reactors, 2011–2015) the geometry and operating conditions of temperature, flow velocity and power density are representative of the fuel assemblies envisaged for the MYRRHA reactor. An extensive test matrix is evaluated, with 33 experimental runs covering a wide range of Reynolds (ca. 14 000–48 000) and Péclet (ca. 400–1500) numbers, as well as thermal powers (up to 295 kW) at 200 °C inlet temperature, indicating a good degree of reproducibility within the relatively small experimental uncertainties. Both the pressure drop and heat transfer performances are studied. When possible, a comparison with correlations available in the reviewed literature (namely, friction and heat transfer coefficients) is given. Furthermore, the detailed cross-sectional temperature distribution at three selected axial positions is obtained in the experiments and represents the main validation data for CFD. In non-dimensional terms, these profiles could be repeated at different operating conditions, for example hot and cold spots are consistently found at given locations.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.nucengdes.2016.03.003Additional details
Identifiers
- DOI
- 10.1016/j.nucengdes.2016.03.003;
- PII
- S0029-5493(16)00116-3;
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 301
- Journal Page Range
- p. 111-127
- ISSN
- 0029-5493
- CODEN
- NEDEAU
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 48005699
- Subject category
- S42: ENGINEERING; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- BISMUTH; COMPARATIVE EVALUATIONS; CORRELATIONS; FLUID FLOW; FUEL ELEMENT CLUSTERS; HEAT; HEAT TRANSFER; LEAD; LIQUID METALS; MYRRHA FACILITY; NUSSELT NUMBER; PRESSURE DROP; REYNOLDS NUMBER; RODS; SPACERS; TEMPERATURE DISTRIBUTION; TEMPERATURE MEASUREMENT; WIRES; WORKING FLUIDS
- Descriptors DEC
- ACCELERATOR-DRIVEN SUBCRITICAL SYSTEMS; DIMENSIONLESS NUMBERS; ELEMENTS; ENERGY; ENERGY TRANSFER; EPITHERMAL REACTORS; EVALUATION; EXPERIMENTAL REACTORS; FAST REACTORS; FLUIDS; FUEL ASSEMBLIES; LIQUIDS; METALS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SUBCRITICAL ASSEMBLIES
Optional Information
- Copyright
- Copyright (c) 2016 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.