In the frame of the validation and verification of the thermal hydraulic system code TRACE for lead alloy cooled systems, a 19 pin bundle is analyzed, in particular, the influence of the spacers. TRACE is updated and improved in order to be used for the analyses of liquid metal cooled reactors. For the present investigation, isothermal hydraulic experiments, carried out at the Karlsruhe Lead Laboratory, are used to validate the pressure losses related to wall friction and spacers. In this experimental set-up, a 19 rod bundle, cooled by liquid lead-bismuth eutectics (LBE) is used. In addition, thermal analyses are performed in order to evaluate the axial temperature profile of coolant and cladding and to validate the chosen heat transfer models. Since the thermal experiments have not been performed yet, the validation is done by comparing TRACE results to CFD results following a unique approach for the turbulent Prandtl number. Special emphasize is paid to the validation of the models to account for heat transfer enhancement at and in the vicinity of spacers due to increased turbulences.
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2013 21st International Conference on Nuclear Engineering
July 29–August 2, 2013
Chengdu, China
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5581-2
PROCEEDINGS PAPER
Thermal-Hydraulic Evaluation of an LBE Cooled 19-Pin Bundle in the Frame of TRACE Validation
Wadim Jaeger,
Wadim Jaeger
Karlsruhe Institute of Technology, Eggenstein-Leopoldshafen, Germany
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Micheal Boettcher,
Micheal Boettcher
Karlsruhe Institute of Technology, Eggenstein-Leopoldshafen, Germany
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Victor Hugo Sánchez Espinoza
Victor Hugo Sánchez Espinoza
Karlsruhe Institute of Technology, Eggenstein-Leopoldshafen, Germany
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Wadim Jaeger
Karlsruhe Institute of Technology, Eggenstein-Leopoldshafen, Germany
Micheal Boettcher
Karlsruhe Institute of Technology, Eggenstein-Leopoldshafen, Germany
Victor Hugo Sánchez Espinoza
Karlsruhe Institute of Technology, Eggenstein-Leopoldshafen, Germany
Paper No:
ICONE21-15327, V004T09A032; 10 pages
Published Online:
February 7, 2014
Citation
Jaeger, W, Boettcher, M, & Sánchez Espinoza, VH. "Thermal-Hydraulic Evaluation of an LBE Cooled 19-Pin Bundle in the Frame of TRACE Validation." Proceedings of the 2013 21st International Conference on Nuclear Engineering. Volume 4: Thermal Hydraulics. Chengdu, China. July 29–August 2, 2013. V004T09A032. ASME. https://doi.org/10.1115/ICONE21-15327
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