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改进型快谱超临界水冷堆子通道CFD数值模拟

Subchannel Analysis of Improved Supercritical Water Cooled Fast Reactor Using CFD Method
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摘要 改进型快谱超临界水冷堆(SCFR-M)具有紧凑的堆芯设计,堆芯内采用增殖组件与点火组件混合排布.增殖组件采用内冷式的圆形冷却剂通道,点火组件则采用典型三角形通道.本文基于CFD软件FLUENT采用流固共轭传热方式,分别对SCFR-M两种冷却剂通道内流动状态进行数值模拟计算,研究了稳态工况下SCFR-M堆芯设计的热工水力特性,计算结果表明:两种子通道中包壳表面温度均小于650℃、燃料芯块中心线温度均小于1 900℃,且流致振动程度在可接受范围内,符合安全设计限值. An improved fast spectrum supercritical water cooled reactor (SCFR-M) with tight fuel pin arrangement is divided into seed and blanket region. The cylindrical water rod is used for the blanket assembly, and the triangular-array fuel rod bundle is used in the seed assembly. In this paper, thermal-hydraulic behavior of supercritical water in subchan- nel of SCFR-M has been investigated using computational fluid dynamics (CFD) code FLUENT. Results show that the maximum cladding surface temperature is below 650℃ and the fuel centerline temperature is below 1900 ℃ in two kinds of subchannel. And the level of flow-induced vibration is in the acceptable range.
出处 《南华大学学报(自然科学版)》 2013年第2期10-15,共6页 Journal of University of South China:Science and Technology
基金 核反应堆系统设计国家重点实验室基金资助项目(2010SYS02) 湖南省教育厅重点基金资助项目(11A101)
关键词 改进型快谱超临界水冷堆 CFD 稳态工况 improved mix supercritical water cooled fast reactor CFD steady state
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参考文献5

  • 1Yoo J, Ishiwatari Y, Oka Y, et al. Conceptual design ofcompact supercritical water-cooled fast reactor with ther- mal hydraulic coupling [ J ]. Annals of Nuclear Energy, 2006,33 (2) : 945-956.
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二级参考文献5

  • 1李满昌,王明利.超临界水冷堆开发现状与前景展望[J].核动力工程,2006,27(2):1-4. 被引量:19
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  • 3Jaewoon Yoo, Yuki Ishiwatari, Yoshiaki Oka. et al. Conceptual Design of Compact Supercritical Water-Cooled Fast Reactor with Thermal Hydraulic Coupling [J]. Annals of Nuclear Energy, 2006, 33: 945-956.
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  • 5陆道纲,彭常宏.超临界水冷堆述评[J].原子能科学技术,2009,43(8):743-749. 被引量:15

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