Many of the highly active waste liquors that result from the reprocessing of spent nuclear fuel contain particulate solids of various materials. Operations for safe processing, handling and intermediate storage of these wastes often pose significant technical challenges due to the need for effective cooling systems to remove the heat generated by the radioactive solids. The multiscale complexity of liquid-particle flow systems is such that investigation and prediction of their heat transfer characteristics based on experimental studies is a difficult task. Fortunately, the increasing availability of cheap computing power means that predictive simulation tools may be able to provide a means to investigate these systems without the need for expensive pilot studies. In this work we describe the development of a Combined Continuum and Discrete Model (CCDM) for predicting the heat transfer behaviour of systems of particles suspended in liquids.
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The 11th International Conference on Environmental Remediation and Radioactive Waste Management
September 2–6, 2007
Bruges, Belgium
Conference Sponsors:
- Nuclear Division and Environmental Engineering Division
ISBN:
978-0-7918-4339-0
PROCEEDINGS PAPER
Development of a Computer Simulation Technique for Predicting Heat Transfer in Multiphase Liquid-Particle Flow Systems
Kevin F. Malone,
Kevin F. Malone
AWE Plc., Aldermaston, Berkshire, England, UK
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Michael Fairweather
Michael Fairweather
University of Leeds, Leeds, UK
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Kevin F. Malone
AWE Plc., Aldermaston, Berkshire, England, UK
Bao H. Xu
University of Leeds, Leeds, UK
Michael Fairweather
University of Leeds, Leeds, UK
Paper No:
ICEM2007-7025, pp. 1039-1046; 8 pages
Published Online:
May 29, 2009
Citation
Malone, KF, Xu, BH, & Fairweather, M. "Development of a Computer Simulation Technique for Predicting Heat Transfer in Multiphase Liquid-Particle Flow Systems." Proceedings of the The 11th International Conference on Environmental Remediation and Radioactive Waste Management. 11th International Conference on Environmental Remediation and Radioactive Waste Management, Parts A and B. Bruges, Belgium. September 2–6, 2007. pp. 1039-1046. ASME. https://doi.org/10.1115/ICEM2007-7025
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