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超临界水冷堆热工水力与安全研发

赵学斌 黄彦平 臧金光

赵学斌, 黄彦平, 臧金光. 超临界水冷堆热工水力与安全研发[J]. 核动力工程, 2023, 44(5): 223-231. doi: 10.13832/j.jnpe.2023.05.0223
引用本文: 赵学斌, 黄彦平, 臧金光. 超临界水冷堆热工水力与安全研发[J]. 核动力工程, 2023, 44(5): 223-231. doi: 10.13832/j.jnpe.2023.05.0223
Zhao Xuebin, Huang Yanping, Zang Jinguang. Research and Development on Thermal Hydraulic and Safety of Supercritical Water-cooled Reactor[J]. Nuclear Power Engineering, 2023, 44(5): 223-231. doi: 10.13832/j.jnpe.2023.05.0223
Citation: Zhao Xuebin, Huang Yanping, Zang Jinguang. Research and Development on Thermal Hydraulic and Safety of Supercritical Water-cooled Reactor[J]. Nuclear Power Engineering, 2023, 44(5): 223-231. doi: 10.13832/j.jnpe.2023.05.0223

超临界水冷堆热工水力与安全研发

doi: 10.13832/j.jnpe.2023.05.0223
详细信息
    作者简介:

    赵学斌(1990—),男,博士,主要从事热工水力方面的研究,E-mail: xbzhao90@126.com

    通讯作者:

    黄彦平,E-mail: hyanping007@163.com

  • 中图分类号: TK124;TL333

Research and Development on Thermal Hydraulic and Safety of Supercritical Water-cooled Reactor

  • 摘要: 超临界水冷堆是第四代核能系统国际论坛确定的六种先进堆型中唯一的水冷堆。由于超临界水作为冷却剂以及超临界水在物理相态的特有属性,使其在热工水力方面有着独特的表现。本文介绍了超临界水冷堆热工水力的总体要求,描述了典型热工水力过程的基本特点及目前主要研发进展,着眼于超临界水冷堆工程提出了后续研发任务,以及未来超临界水冷堆的发展建议。

     

  • 图  1  简化堆芯多组件的并联通道示意图

    Figure  1.  Schematic of Simplified Parallel Channels

    图  2  SCWR 2×2棒束子通道一般划分

    1—中心通道;2—角通道;3—边通道

    Figure  2.  General Division of Sub-channels of SCWR 2×2 Rod Bundle

    表  1  国内外超临界水临界流动实验

    Table  1.   Experiments on Critical Flow of Supercritical Water at Home and Abroad



    实验单位
    国家
    实验压力
    /MPa
    实验段直径
    /mm
    实验段
    长径比
    英国电力能源研究所[33] 英国 22~31 1.78、2.54 1、3
    中国原子能科学研究院[34-35] 中国 22.1~29.1 1.41 3
    加拿大蒙特利尔综合理工学院[36] 加拿大 22.0~32.1 1 3
    下载: 导出CSV
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出版历程
  • 收稿日期:  2023-01-16
  • 修回日期:  2023-07-25
  • 刊出日期:  2023-10-13

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