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矩形窄缝通道底部再淹没实验研究

邓永皓 许巍 刘晓晶 郭玖元 吴丹

邓永皓, 许巍, 刘晓晶, 郭玖元, 吴丹. 矩形窄缝通道底部再淹没实验研究[J]. 核动力工程, 2021, 42(6): 17-23. doi: 10.13832/j.jnpe.2021.06.0017
引用本文: 邓永皓, 许巍, 刘晓晶, 郭玖元, 吴丹. 矩形窄缝通道底部再淹没实验研究[J]. 核动力工程, 2021, 42(6): 17-23. doi: 10.13832/j.jnpe.2021.06.0017
Deng Yonghao, Xu Wei, Liu Xiaojing, Guo Jiuyuan, Wu Dan. Experimental Study of Bottom Reflooding in a Narrow Rectangular Channel[J]. Nuclear Power Engineering, 2021, 42(6): 17-23. doi: 10.13832/j.jnpe.2021.06.0017
Citation: Deng Yonghao, Xu Wei, Liu Xiaojing, Guo Jiuyuan, Wu Dan. Experimental Study of Bottom Reflooding in a Narrow Rectangular Channel[J]. Nuclear Power Engineering, 2021, 42(6): 17-23. doi: 10.13832/j.jnpe.2021.06.0017

矩形窄缝通道底部再淹没实验研究

doi: 10.13832/j.jnpe.2021.06.0017
基金项目: 国家青年基金(11922505)
详细信息
    作者简介:

    邓永皓(1996—),硕士研究生,主要从事反应堆热工水力研究工作,E-mail: _Watanabe_@sjtu.edu.cn

    通讯作者:

    刘晓晶,E-mail: xiaojingliu@sjtu.edu.cn

  • 中图分类号: TL364

Experimental Study of Bottom Reflooding in a Narrow Rectangular Channel

  • 摘要: 为了解矩形窄缝通道在失水事故(LOCA)下底部再淹没过程中的热工水力特性,在不同实验条件下开展再淹没实验研究。矩形窄缝通道由2块因科镍合金焊接而成,本研究根据温度变化曲线分析底部再淹没过程,计算并对比不同实验工况下的骤冷前沿的推进速度(骤冷速度),以及研究实验参数对再淹没过程的影响。实验结果表明,底部再淹没骤冷速度随着系统压力增大、进口流速增大、初始壁面温度降低以及冷却水过冷度的增大而增大。对比分析底部与联合再淹没工况,结果表明流量相同的情况下,底部再淹没的骤冷速度大于联合再淹没。本文研究为板状燃料元件反应堆事故预防以及事故缓解等研究奠定了基础。

     

  • 图  1  实验回路示意图

    Figure  1.  Sketch of the Experimental Loop

    图  2  实验段截面图

    Figure  2.  Cross-sectional View of the Test Section

    图  3  热电偶位置分布图

    Figure  3.  Positions of Thermocouples

    图  4  工况①下TC-3、4、5的测量温度

    骤冷温度—再淹没过程中壁面温度开始显著下降的温度;再湿温度—冷却水开始接触壁面的温度[5]

    Figure  4.  Temperatures of TC-3, 4 and 5 in Case ①

    图  5  工况①下实验开始阶段TC-3、4、5温度变化曲线

    Figure  5.  Temperature Variation Curve of TC-3, 4 and 5 at the Beginning of Experiment in Case ①

    图  6  工况①下TC-3中的温度变化率

    Figure  6.  Temperature Variation Rate of TC-3 in Case ①

    图  7  工况①、②下TC-4温度变化曲线

    Figure  7.  Temperature Variation Curve of TC-4 in Case ① and ②

    图  8  工况①、③、④下TC-4温度变化曲线

    Figure  8.  Temperature Variation Curve of TC-4 in Case ①, ③ and ④     

    图  9  工况①、⑤下TC-4温度变化曲线

    Figure  9.  Temperature Variation Curve of TC-4 in Cases ① and ⑤      

    图  10  工况①、⑤下夹带水箱内水体积变化曲线

    Figure  10.  Variation Curve of Water Volume in Entrained Water Tank in Cases ① and ⑤

    图  11  工况①、⑥、⑦下TC-4温度变化情况

    Figure  11.  Temperature Variation Curve of TC-4 in Cases ①, ⑥ and ⑦      

    图  12  TC-4在工况④、⑧、⑨、⑩下温度变化曲线

    Figure  12.  Temperature Variation Curve of TC-4 in Cases ④, ⑧, ⑨ and ⑩

    表  1  底部再淹没实验工况

    Table  1.   Experimental Cases of Bottom Reflooding

    工况加热板壁温/
    压力/
    105Pa
    进口水温/
    入口流速/
    (cm·s−1)
    613.231.0135.775.55
    522.441.0133.395.86
    645.911.0132.482.79
    606.011.0134.8111.72
    629.851.0190.665.80
    603.881.9651.585.63
    646.154.0970.895.62
    下载: 导出CSV

    表  2  工况①实验开始阶段TC-3、4、5温度转折时间及温度下降速率

    Table  2.   Temperature Transition Time and Temperature Drop Rate of TC-3, 4 and 5 at the Beginning of Experiment in Case ①

    参数TC-3TC-4TC-5
    温度转折时间/s9.6715.0024.33
    温度下降速率/(℃·s−1)−0.183−0.078−0.026
    下载: 导出CSV

    表  3  各工况下的骤冷、再湿速度

    Table  3.   Quench and Rewetting Speed in All Cases

    工况平均温度/℃速度/(mm·s−1)
    骤冷再湿骤冷再湿
    522.58361.681.972.01
    464.89314.812.342.47
    588.36345.141.441.25
    525.45345.273.223.08
    515.71321.901.331.28
    499.08359.952.752.91
    515.15393.353.433.55
    下载: 导出CSV

    表  4  联合再淹没工况

    Table  4.   Combined Reflooding Cases

    工况加热板
    壁温/℃
    进口
    水温/℃
    底部进口流速/
    (cm·s−1)
    顶部进口流速/
    (cm·s−1)
    639.4733.773.068.66
    609.9034.885.765.85
    607.8230.728.643.04
    下载: 导出CSV

    表  5  联合再淹没骤冷、再湿速度

    Table  5.   Quench, Rewetting Speed of Combined Reflooding

    工况平均温度/℃速度/(mm·s−1)
    骤冷再湿骤冷再湿
    525.45345.273.223.08
    556.16332.461.261.22
    459.00309.571.992.14
    513.02342.862.732.80
    下载: 导出CSV
  • [1] KIMBALL K D, ROY R P. Quench front propagation during bottom reflooding of a heated annular channel[J]. Nuclear Engineering & Design, 1983, 76(1): 79-88.
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    [12] 王金宇,王均,昝元峰,等. 环形通道内再淹没过程骤冷前沿推进速度实验研究[J]. 核动力工程,2018, 39(4): 63-66.
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出版历程
  • 收稿日期:  2020-11-16
  • 修回日期:  2021-05-25
  • 刊出日期:  2021-12-09

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