Laminar fluid flow and heat transfer in non-circular sub-channel geometries of nuclear fuel bundle
Author:
Publisher
Elsevier BV
Subject
Waste Management and Disposal,Energy Engineering and Power Technology,Safety, Risk, Reliability and Quality,Nuclear Energy and Engineering
Reference23 articles.
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3. Pressure drop of fully developed Laminar flow in microchannels of arbitrary cross-section;Bahrami,2005
4. Combined forced and free flow in a vertical rectangular duct with prescribed wall heat flux;Barletta;Int. J. Heat Fluid Flow,2003
5. Peripheral temperature variation in the wall of a non-circular duct - an experimental investigation;Barrow;Int. J. Heat Mass Transf.,1984
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1. Modeling single-phase transverse flows in a PWR rod bundle at low Reynolds number;Nuclear Engineering and Design;2024-01
2. Natural Convection Through and Over a Heating Porous Medium:Towards High Fidelity Simulations of Nuclear Spent Fuel Pools;2023
3. Development of analytical models for the natural circulation behavior of a full-scale PWR fuel assembly;Annals of Nuclear Energy;2022-09
4. Impact of round edge on the duct fluid flow: analytical investigation;SN Applied Sciences;2021-03-06
5. Numerical study of time-dependent ferrofluid flow past a cylinder in the presence of stationary magnetic field;SN Applied Sciences;2021-01
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