In paper the thermal stratification of liquid lead–bismuth eutectic in accelerator driven subcritical system (ADS) under LOCA is investigated. By means of establishing the space geometric distribution model of thermal stratification which produced in ADS interspace as well as using H2TS scaling analysis to simulate the phenomenon, the main parameters of model facility can be calculated and discussed. When the geometric scaling ratio is chosen be 1/10, by analyzing the Ri number, we can get scaling ratio of leak fluid velocity U0 and process time τ in model is 1/3.16 of the prototype, leak fluid flow Q0 and power q is 1/316.23 of the prototype in the formation process of thermal stratification. Moreover, scaling distortion quantitative analysis for the scaling simulation results be made. So the law related to the time, speed change and so on can be researched, all these work would provide reference and theory for testing facility constructing and ADS safety analysis.
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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
Scaling Analysis of Liquid Lead–Bismuth Eutectic Thermal Stratification in ADS Facility Under LOCA Available to Purchase
Ziwei Su,
Ziwei Su
North China Electric Power University, Beijing, China
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Tao Zhou,
Tao Zhou
North China Electric Power University, Beijing, China
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Yunbo Li,
Yunbo Li
North China Electric Power University, Beijing, China
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Yican Wu
Yican Wu
Chinese Academy of Sciences, Hefei, Anhui, China
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Ziwei Su
North China Electric Power University, Beijing, China
Tao Zhou
North China Electric Power University, Beijing, China
Yunbo Li
North China Electric Power University, Beijing, China
Yican Wu
Chinese Academy of Sciences, Hefei, Anhui, China
Paper No:
ICONE21-15572, V002T05A012; 5 pages
Published Online:
February 7, 2014
Citation
Su, Z, Zhou, T, Li, Y, & Wu, Y. "Scaling Analysis of Liquid Lead–Bismuth Eutectic Thermal Stratification in ADS Facility Under LOCA." 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. V002T05A012. ASME. https://doi.org/10.1115/ICONE21-15572
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