Nuclear Fuel Route Thermal Hydraulics Analysis for Advanced Gas-cooled Reactors ( AGRs )

Trinca, Cosimo (2019) Nuclear Fuel Route Thermal Hydraulics Analysis for Advanced Gas-cooled Reactors ( AGRs ). PhD thesis, University of Sheffield.

Abstract

Metadata

Supervisors: He, Shuisheng and Li, Jiankang
Keywords: Advanced Gas-cooled Reactor, Nuclear Fuel Route, Nuclear Thermal-Hydraulics, Computational Fluid Dynamics, Large Eddy Simulation, Porous Media, Conjugate Heat Transfer
Awarding institution: University of Sheffield
Academic Units: The University of Sheffield > Faculty of Engineering (Sheffield) > Mechanical Engineering (Sheffield)
Identification Number/EthosID: uk.bl.ethos.778835
Depositing User: Mr. Cosimo Trinca
Date Deposited: 16 Jul 2019 13:23
Last Modified: 01 Feb 2020 10:53

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