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Reference Number EP/R021805/1
Title Development and Validation of Thermal-Hydraulic ... in BWR's and PWR's: Can modern CFD models reliably predict DNB for nuclear power applications?
Status Started
Energy Categories NUCLEAR FISSION and FUSION(Nuclear Fission, Nuclear supporting technologies) 100%;
Research Types Basic and strategic applied research 100%
Science and Technology Fields PHYSICAL SCIENCES AND MATHEMATICS (Physics) 100%
UKERC Cross Cutting Characterisation Not Cross-cutting 100%
Principal Investigator Dr S Walker
No email address given
Department of Mechanical Engineering
Imperial College London
Award Type Standard
Funding Source EPSRC
Start Date 01 September 2018
End Date 31 August 2022
Duration 48 months
Total Grant Value £595,241
Industrial Sectors Energy
Region London
Programme Energy : Energy
Investigators Principal Investigator Dr S Walker , Department of Mechanical Engineering, Imperial College London (99.997%)
  Other Investigator Dr R Issa , Department of Mechanical Engineering, Imperial College London (0.001%)
Dr I Hardalupas , Department of Mechanical Engineering, Imperial College London (0.001%)
Professor M Fairweather , Inst of Particle Science & Engineering, University of Leeds (0.001%)
Web Site
Abstract The United Kingdom government has decided that continued use of nuclear power should be made to contribute to a low-carbon electricity generating system in the United Kingdom. It is important that new nuclear plants are designed to be as safe as possible, and this research will contribute to this.Broadly, when a water-cooled nuclear reactor remains cooled by water, it is essentially impossible for it to overheat and suffer damage. Conversely, when the water coolant turns inadvertently to steam this possibility does arise. This project is aimed at developing better predictive tools to understand when the change of coolant from liquid water to steam occurs. Better predictive capability here will allow new plants to be designed with even more confidence as to their safety.This project will be undertaken in collaboration with our colleagues in the Indian civil nuclear power industry, specifically at the Bhaba Atomic Research Centre in Mumbai. Here our Indian colleagues, supported by the United Kingdom team, will engage in complex measurements of the boiling process, and of the turning of the liquid water coolant into steam. Alongside these measurements, we and they will develop sophisticated computational predictive tools for this change from liquid water to steam. These predictive tools will study the fundamental physics of the boiling process, right down at a scale of a few microns, and will extend to the construction and validation of predictive tools applied to the scale of whole portions of the nuclear core.The quality and effectiveness of the predictive tools to be developed will be able to be assessed by comparing their predictions with the observed occurrence of this water-steam transition.
Publications (none)
Final Report (none)
Added to Database 11/10/18