Molten salt reactor was one of six Generation IV reactor types, which uses the liquid molten salt as the coolant and fuel solvent. In transmutation of actinides and long-lived fission products have marked advantages. As a liquid reactor the physical property and thermo-characteristic is different to solid fuel and water coolant reactors, which was influenced by many factors. MOSART was one of the advanced molten salt reactors concept design, which can burners TRU from LWR spent fuel. The reactor core does not contain graphite structure elements, so the flow pattern was potentially complex and may significantly affect the fuel temperature distributions. The optimizations of the salt flow may be needed, the present work designed three core models and three kinds of distribution plates to investigate the influence of lower plenum and distribution plates to thermohydraulics characteristics of the reactor core with CFD method use software FLUENT. Velocity field and maximum temperature of the core was simulated in each model at different mass flow rate.
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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 Optimization Design of Lower Plenum and Distribution Plates in MSR
Jianjun Zhou,
Jianjun Zhou
Xi’an Jiaotong University, Xi’an, China
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Suizheng Qiu,
Suizheng Qiu
Xi’an Jiaotong University, Xi’an, China
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Zhangpeng Guo,
Zhangpeng Guo
Xi’an Jiaotong University, Xi’an, China
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Guanghui Su
Guanghui Su
Xi’an Jiaotong University, Xi’an, China
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Jianjun Zhou
Xi’an Jiaotong University, Xi’an, China
Suizheng Qiu
Xi’an Jiaotong University, Xi’an, China
Zhangpeng Guo
Xi’an Jiaotong University, Xi’an, China
Guanghui Su
Xi’an Jiaotong University, Xi’an, China
Paper No:
ICONE21-16436, V002T03A049; 11 pages
Published Online:
February 7, 2014
Citation
Zhou, J, Qiu, S, Guo, Z, & Su, G. "The Optimization Design of Lower Plenum and Distribution Plates in MSR." 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. V002T03A049. ASME. https://doi.org/10.1115/ICONE21-16436
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