Projects
Projects: Projects for Investigator |
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| Reference Number | EP/M018261/1 | |
| Title | Indo - UK: Premature, Oscillation-Induced Critical Heat Flux ("Premature OICHF") | |
| Status | Completed | |
| 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) 25%; ENGINEERING AND TECHNOLOGY (Mechanical, Aeronautical and Manufacturing Engineering) 75%; |
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| 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 December 2015 | |
| End Date | 30 November 2018 | |
| Duration | 36 months | |
| Total Grant Value | £112,729 | |
| 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 MJ Bluck , Department of Mechanical Engineering, Imperial College London (0.001%) Professor GF Hewitt , Chemical Engineering, Imperial College London (0.001%) |
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| Web Site | ||
| Objectives | ||
| Abstract | Water is an excellent coolant for nuclear reactors, but steam is a very poor one. The ability to predict with confidence, but without excessive conservatism, the point at which cooling by water will turn into cooling by just steam is absolutely vital. The the rate of transfer of heat at which this transition occurs is known as the "critical heat flux" (CHF).Predicting the circumstances under which CHF would occur (and then making sure that reactor operating conditions stay well away from them) is a very large part of the thermal hydraulic design of water cooled reactors.There are some, unusual, circumstances in which the flows inside a nuclear reactor can become unsteady and cyclical, with flow-rates rising and falling with time. Under the circumstances, predicting the critical heat flux not surprisingly becomes rather more complicated and difficult.This project is attempting to build a computer model which will predict when critical heat flux occurs in the presence of cyclical flows. The second strand of this project is to conduct experiments in which a test section is exposed to a cyclical flow, and the occurrence or not of critical heat flux is observed. The model we develop will then be tested and refined against these measurements. A validated, general-purpose tool for predicting critical heat flux under conditions of oscillatory flow will be a useful additional capability available to reactor designers and safety analysts | |
| Publications | (none) |
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| Final Report | (none) |
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| Added to Database | 24/08/16 | |
