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Validation of a CFD Code Star-CCM+ for Liquid Lead-Bismuth Eutectic Thermal-Hydraulics Using TALL-3D Experiment
KTH, School of Engineering Sciences (SCI), Physics, Nuclear Power Safety.ORCID iD: 0000-0001-5653-9206
KTH, School of Engineering Sciences (SCI), Physics, Nuclear Power Safety.
KTH, School of Engineering Sciences (SCI), Physics, Nuclear Power Safety.ORCID iD: 0000-0003-3132-7252
KTH, School of Engineering Sciences (SCI), Physics, Nuclear Power Safety.
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2014 (English)Conference paper, Published paper (Refereed)
Abstract [en]

The engineering design, performance analysis and safety assessment of Generation IV heavy liquid metal cooled nuclear reactors calls for advanced and qualified numerical tools. These tools need to be qualified before used in decision making process. Computational Fluid Dynamics (CFD) codes provide detailed means for thermal-hydraulics analysis of pool-type nuclear reactors. This paper describes modeling of a forced to natural flow experiment in TALL-3D experimental facility using a commercial CFD code Star-CCM+. TALL-3D facility is 7 meters high LBE loop with two parallel hot legs and a cold leg. One of the hot legs accommodates the 3D test section, a cylindrical pool where the multi-dimensional flow conditions vary between thermal mixing and stratification depending on the mass flow rate and the power of the heater surrounding the pool. The pool outlet temperature which affects the natural convection flow rates in the system is governed by the flow structure in the pool. Therefore, in order to predict the dynamics of the TALL-3D facility it is crucial to resolve the flow inside the 3D test section. Specifically designed measurement instrumentation set-up provides steady state and transient data for calibration and validation of numerical models. The validity of the CFD model is assessed by comparing the computational results to experimental results.

Place, publisher, year, edition, pages
Atomic Energy Society of Japan , 2014.
Keyword [en]
CFD, Validation, TALL - 3D, LFR
National Category
Other Engineering and Technologies not elsewhere specified
Identifiers
URN: urn:nbn:se:kth:diva-164075OAI: oai:DiVA.org:kth-164075DiVA: diva2:803097
Conference
The 10th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety (NUTHOS-10) NUTHOS10-1269 Okinawa, Japan, December 14-18, 2014
Note

QC 20150427

Available from: 2015-04-13 Created: 2015-04-13 Last updated: 2015-04-27Bibliographically approved

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fulltext(1391 kB)143 downloads
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Jeltsov, MartiVillanueva, WalterKudinov, Pavel

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CiteExportLink to record
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