Numerical simulation of buoyant flow in a vertical channel for a plasma-facing component
Author:
Funder
National Institute for Fusion Science
National Institutes for Quantum Science and Technology
Publisher
Elsevier BV
Reference14 articles.
1. Numerical simulation of turbulent flow of coolant in a test blanket module of nuclear fusion reactor;Seki;Prog. Nucl. Sci. Technol.,2011
2. Thermo-hydraulic testing and integrity of ITER Test Blanket Module (TBM) First Wall mock-up in JAEA;Ezato;Fusion Eng. Des.,2010
3. Buoyancy effects in vertical rectangular duct with coplanar magnetic field and single sided heat load Downward and upward flow;Kirillova;Fusion Eng. Des.,2018
4. Critical heat flux analysis and R&D for the design of the ITER divertor;Raffray;Fusion Eng. Des.,1999
5. Numerical and experimental study of coolant water flow in ITER divertor outer vertical target;Seki;Fusion Eng. Des.,2018
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