About the Project
During a LOCA event, the resulting boiling leads to the formation and transport of bubbles of vapour by the high velocity coolant fluid. Bubbles can form clusters or coalesce, resulting in vapour clots or slug flows in the narrow reactor core channels, which in turn affect the designed coolant heat flux. The resulting large temperature system can potentially damage the solid structures (cladding and fuel rods) leading to core melting and fragmentation.
This project aims to improve our understanding of the initial LOCA stages that may lead to a reactor core melting. The project will exploit existing stateof-the-art computational methods to investigate CHF in tube bundles during a LOCA event. This will involve the development of CFD models for:
(a) Multi-scale heat and fluid flows using high-order accurate schemes coupled with adaptive LES turbulent methods;
(b) Heterogeneous and homogeneous nucleation mechanisms; and
(c) Prediction of heat transfer and bubble size distribution.
Candidates should have (or expect to achieve) a UK honours degree at 2.1 or above (or equivalent) in Physics, Mathematics, Computational Sciences, Nuclear, Mechanical, Chemical or Civil Engineering.
Essential Knowledge: Fluid mechanics, heat and mass transfers, thermodynamics and computational methods.
Fluid dynamics; Numerical methods; Computational linear algebra; Fortran or Python or C languages.
• Apply for Degree of Doctor of Philosophy in Engineering
• State name of the lead supervisor as the Name of Proposed Supervisor
• State ‘Self-funded’ as Intended Source of Funding
• State the exact project title on the application form
When applying please ensure all required documents are attached:
• All degree certificates and transcripts (Undergraduate AND Postgraduate MSc-officially translated into English where necessary)
• Detailed CV
Informal inquiries can be made to Dr J Gomes (Jefferson.firstname.lastname@example.org), with a copy of your curriculum vitae and cover letter. All general enquiries should be directed to the Postgraduate Research School (email@example.com)
Design 262: 544-561.
J. Gomes et al. (2011) Coupled Neutronics-Fluids Modelling of Criticality within a MOX Powder System, Progress in Nuclear Energy 53: 523-552.
Buchan et al. (2012) Simulated Transient Dynamics and Heat Transfer Characteristics of the Water Boiler Nuclear Reactor – SUPO – with
Cooling Coil Heat Extraction, Annals of Nuclear Energy 48: 68-83.
S.Mimouni et al. (2011) Combined Evaluation of 2nd-Order Turbulence Model and Polydispersion Model for Two-Phase Boiling Flow and
Application to Fuel Assembly Analysis, Nuclear Engineering and Design 241: 4523-4536.
Why not add a message here
Based on your current searches we recommend the following search filters.
Based on your current search criteria we thought you might be interested in these.