Numerical Analysis of Effects of Vane Deflection Angle on Flow-Thermal Characteristics in a Fuel Rod Assembly
Author:
Affiliation:
1. National Institute of Technology Raipur, Mechanical Engineering Department, Raipur (C.G)-492010, India
2. National Institute of Technology Durgapur, Mechanical Engineering Department, West Bengal-713209, India
Publisher
Informa UK Limited
Link
https://www.tandfonline.com/doi/pdf/10.1080/00295450.2024.2309080
Reference36 articles.
1. Z. KAROUTAS, C. GU, and B. SHOLIN, “3-D Flow Analyses for Design of Nuclear Fuel Spacer,” Proc. 7th Int. Mtg. on Nuclear Reactor Thermal-Hydraulics (NURETH-7), p. 3153, New York (1995).
2. CFD simulation of heated tight-lattice rod bundles for an IAEA benchmark
3. Augmentation of single-phase forced convection heat transfer in tightly arrayed rod bundle with twist-vane spacer grid
4. Effects of Mixing Vane Spacer on Flow and Thermal Behavior of Fluid in Fuel Channels of Nuclear Reactors—A Review
5. CFD simulation of flow and heat transfer characteristics in a 5×5 fuel rod bundles with spacer grids of advanced PWR
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