Department: Department of Mechanical Engineering
Organisation: Imperial College London
COMPUTATIONAL MODELLING FOR ADVANCED NUCLEAR POWER PLANTS
Development and Validation of Thermal-Hydraulic ... in BWR's and PWR's: Can modern CFD models reliably predict DNB for nuclear power applications?
Grace Time
Indo - UK: Premature, Oscillation-Induced Critical Heat Flux ("Premature OICHF")
Indo-UK Civil Nuclear Network
Investigations of HTGR Reactor Building Response to Break in Primary Coolant Boundary
Thermal Hydraulics for Boiling and Passive Systems
Validation & Verification for Critical Heat Flux and CFD
Enhanced Methodologies for Advanced Nuclear System Safety (eMEANSS)
Keeping the Nuclear Option Open
UKINN: UK India Nuclear Network
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