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| 引用本文： | 王小勇,栗再新,赵奉超,赵周,武兴华,王琦杰.???-?????????????????????????????[J].核聚变与等离子体物理,2014,34(4):320-325. |
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| 作者姓名： | 王小勇 栗再新 赵奉超 赵周 武兴华 王琦杰 |
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| 作者单位： | (?????????????о???????610041) |
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| 摘 要： | 对新提出的套管结构聚变-快裂变增殖堆包层概念设计方案进行了热工水力学分析和设计,给出了典型的热工设计参数,并结合大型热工水力学软件CFX对其进行了温度场和压力分布的模拟分析。分析结果表明,材料温度均已低于许用温度,冷却剂出口温度高于773K,冷却剂压降也符合工程上的要求,初步验证了增殖堆包层设计的合理性。
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| 关 键 词： | 聚变-快裂变增殖堆 包层 热工水力学 CFX软件 |
Preliminary thermal-hydraulic design and simulation for hybrid breeder blanket |
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| WANG Xiao-yong,LI Zai-xin,ZHAO Feng-chao,ZHAO Zhou,WU Xing-hua,WANG Qi-jie.Preliminary thermal-hydraulic design and simulation for hybrid breeder blanket[J].Nuclear Fusion and Plasma Physics,2014,34(4):320-325. |
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| Authors: | WANG Xiao-yong LI Zai-xin ZHAO Feng-chao ZHAO Zhou WU Xing-hua WANG Qi-jie |
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| Institution: | (Southwest Institute of Physics, Chengdu 610041) |
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| Abstract: | Thermal-hydraulic design and analysis for the new conceptual design of fusion-fission breeding reactor using casing pipes for fuel assembly was done. Based on typical thermal-hydraulic design parameters, preliminary thermal-hydraulic design for the blanket was proposed. The corresponding temperature distribution and pressure distribution were obtained using thermal-hydraulic codes, CFX. The simulation results showed that maximum temperature of the materials were all below their corresponding temperature limits, coolant temperature at the outlet was higher than 773 , and pressure drop of the coolant could satisfy engineering requirement. T ?? he reasonability of this thermal-hydraulic design was preliminarily verified. |
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| Keywords: | Fusion-fission breeding reactor Blanket Thermal-hydraulics CFX code |
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