Experimental study on the heat transfer enhancement in sub-channels of 6 × 6 rod bundle with large scale vortex flow mixing vanes

Author:

Byun Sun-JoonORCID,Shin Chang-Hwan,Yoon JungORCID,Kim Hyungmo,Lee Jewhan,Eoh Jaehyuk,Jeong Ji-Young

Funder

NRF

MSIP

Ministry of Science, ICT&Future Planning

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference26 articles.

1. A Simulation of Turbulent Structure Variation in the Sub-channel of Nuclear Reactor Rod Bundle by Large Scale Vortex Flow;An,2007

2. A study of turbulence generation characteristics of large scale vortex flow mixing vane of nuclear fuel rod bundle;An;Soc. Air-Cond. Ref. Eng. Korea,2006

3. Heat Transfer in a Decaying Vortex System. ASME Paper No. 66-WA/HT-62;Blum,1996

4. Validation of the assert subchannel code: prediction of critical heat flux in standard and nonstandard CANDU bundle geometries;Carver;Nucl. Technol.,1995

5. Phenomenological investigations on the turbulent flow structures in a rod bundle array with mixing devices;Chang;Nucl. Eng. Des.,2008

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