The present work was undertaken to evaluate the sedimentation rate of the sodium aerosol in a hypothetical sodium fire accident of China Experimental Fast Reactor (CEFR). In the sodium fire accident, sodium aerosol which was hazardous for facility and people as a result of its chemical property and radioactivity, must be carefully evaluated. In this publication, the chemical and physical characteristics of sodium aerosol particles as well as factors that influence the sedimentation rate of sodium aerosol during its transport is attempted to be analysed. Besides, a simplified model is given to calculate the sedimentation rate when aerosol getting through the sodium fire ventilation system of CEFR. It has been found that the sedimentation rate is largely determined by gravity and turbulent diffusion; other factors, such as Brownian movement and thermophoretic force, could be ignored, since they almost have little effect. Using the model, we find that the loss through the ventilation system is about 5%.
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2013 21st International Conference on Nuclear Engineering
July 29–August 2, 2013
Chengdu, China
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5579-9
PROCEEDINGS PAPER
The Analysis of Sedimentation Rate of Sodium Aerosol in a Hypothetical Accident of CEFR
Dajie Sun,
Dajie Sun
China Institute of Atomic Energy, Beijing, China
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Donghui Zhang,
Donghui Zhang
China Institute of Atomic Energy, Beijing, China
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Lixia Ren
Lixia Ren
China Institute of Atomic Energy, Beijing, China
Search for other works by this author on:
Dajie Sun
China Institute of Atomic Energy, Beijing, China
Donghui Zhang
China Institute of Atomic Energy, Beijing, China
Lixia Ren
China Institute of Atomic Energy, Beijing, China
Paper No:
ICONE21-16140, V002T05A042; 6 pages
Published Online:
February 7, 2014
Citation
Sun, D, Zhang, D, & Ren, L. "The Analysis of Sedimentation Rate of Sodium Aerosol in a Hypothetical Accident of CEFR." Proceedings of the 2013 21st International Conference on Nuclear Engineering. Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors. Chengdu, China. July 29–August 2, 2013. V002T05A042. ASME. https://doi.org/10.1115/ICONE21-16140
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