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http://dx.doi.org/10.5407/JKSV.2011.9.4.054

Water-Simulant Facility Installation for the Sodium-Cooled Fast Reactor KALIMER-600 and Global Flow Measurement  

Cha, Jae-Eun (한국원자력연구원 고속로기술개발부)
Kim, Seong-O (한국원자력연구원 고속로기술개발부)
Publication Information
Journal of the Korean Society of Visualization / v.9, no.4, 2011 , pp. 54-62 More about this Journal
Abstract
KAERI has developed a KALIMER-600 which is a pool-type sodium-cooled fast reactor with a 600MWe electric generation capacity. For a SFR development, one of the main topics is an enhancement of the reactor system safety. Therefore, we have a long-term plan to design the large sodium experimental facility to evaluate the reactor safety and component performance. In order to extrapolate a thermal hydraulic phenomena in a large sodium reactor, the thermal hydraulics phenomena is under investigation in a 1/$10^{th}$ water-simulant facility for the KALIMER-600. In this paper, we shortly described the experimental facility setup and the measurement of the isothermal global flow behavior. For the flow field measurement, the PIV method was used in a transparent Plexiglas reactor vessel model at around $20^{\circ}C$ water condition.
Keywords
Sodium-cooled Fast Reactor; Similarity Experiment; Flow Visualization;
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  • Reference
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