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Experimental study on leak flow rate characteristics of high pressure subcooled water through axial and circumferential microcracks of steam generator tubes under high back pressure conditions

机译:高压蒸汽通过蒸汽发生器管轴向和周向微裂纹漏流量特性在高压条件下的实验研究

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摘要

Leak-before-break analyses on tube microcracks are beneficial for preventing small loss of coolant accident in nuclear power plants. Specially, the tube leakage of steam generator may lead to steam generator tube rupture. Currently, experimental investigations on leak flow rate characteristics of normal temperature water and high pressure subcooled water through axial and circumferential microcracks of steam generator tubes were carried out, respectively. Cold Test results indicate that leak flow rates of circumferential microcracks for 0.13 = W = 0.16 mm and 3.6 = delta/D-h = 4.4 increase with a decreasing back pressure (P-out) first and then can be regarded as a constant value for a given working pressure in steam generator tubes (P-in). Additionally, each of Pin has a critical differential pressure between P-in and P-out (Lambda P-c). The ratio of Lambda P-c to P-in is equal to 0.55, which is smaller than 0.64 for axial microcracks. Hot Test results show that leak flow rates decrease significantly with an increasing working fluid temperature (T-f, in) when T-f, in is larger than a certain value due to the flashing of subcooled water near exits of microcracks. Besides, discharge coefficients of high pressure subcooled water through axial and circumferential microcracks under various back pressure conditions decreases with an increasing P-in for a given subcooled temperature. In general, new correlations were developed to give excellent predictions for the leak flow rate data of normal temperature water and high pressure subcooled water through axial and circumferential microcracks of steam generator tubes under various back pressure conditions with a maximum deviation of +/- 6%. (C) 2020 Elsevier Ltd. All rights reserved.
机译:管道微裂纹的泄漏分析有利于防止核电站冷却液事故的小损失。特别地,蒸汽发生器的管泄漏可能导致蒸汽发生器管破裂。目前,分别进行了通过轴向和圆周微裂纹的常温水和高压脱硫水的泄漏流量特性的实验研究。冷测试结果表明,周向微裂纹的泄漏流速0.13 <= w <= 0.16mm和3.6 <= delta / dh <= 4.4随着反压(p-out)的减小而增加,然后可以被视为常数蒸汽发生器管中给定工作压力的值(p-in)。另外,每个引脚在p-in和p-out(lambda p-c)之间具有临界微分压力。 Lambda P-C至p-In的比例等于0.55,用于轴向微裂纹小于0.64。热试验结果表明,由于T-F的工作流体温度(T-F,IN)增加,泄漏流速显着降低,其大于由于沿着微裂纹的靠近过冷水的闪光而大于一定值。此外,在各种后压条件下通过轴向和周向微裂纹的放电系数随着给定的过冷温度的增加而降低。通常,开发了新的相关性,为常温水和高压过冷水的泄漏流量数据通过蒸汽发生器管的轴向和周向微裂纹提供了优异的预测,其在各种背压条件下,最大偏差为+/- 6% 。 (c)2020 elestvier有限公司保留所有权利。

著录项

  • 来源
    《Annals of nuclear energy》 |2020年第9期|107551.1-107551.14|共14页
  • 作者单位

    Xi An Jiao Tong Univ Sch Nucl Sci & Technol State Key Lab Multiphase Flow Power Engn Shanxi Key Lab Adv Nucl Technol 28 Xianning West Rd Xian 710049 Peoples R China;

    Xi An Jiao Tong Univ Sch Nucl Sci & Technol State Key Lab Multiphase Flow Power Engn Shanxi Key Lab Adv Nucl Technol 28 Xianning West Rd Xian 710049 Peoples R China;

    Xi An Jiao Tong Univ Sch Nucl Sci & Technol State Key Lab Multiphase Flow Power Engn Shanxi Key Lab Adv Nucl Technol 28 Xianning West Rd Xian 710049 Peoples R China;

    Xi An Jiao Tong Univ Sch Nucl Sci & Technol State Key Lab Multiphase Flow Power Engn Shanxi Key Lab Adv Nucl Technol 28 Xianning West Rd Xian 710049 Peoples R China;

    Xi An Jiao Tong Univ Sch Nucl Sci & Technol State Key Lab Multiphase Flow Power Engn Shanxi Key Lab Adv Nucl Technol 28 Xianning West Rd Xian 710049 Peoples R China;

    Xi An Jiao Tong Univ Sch Nucl Sci & Technol State Key Lab Multiphase Flow Power Engn Shanxi Key Lab Adv Nucl Technol 28 Xianning West Rd Xian 710049 Peoples R China;

    Xi An Jiao Tong Univ Sch Nucl Sci & Technol State Key Lab Multiphase Flow Power Engn Shanxi Key Lab Adv Nucl Technol 28 Xianning West Rd Xian 710049 Peoples R China;

  • 收录信息
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

    Leak flow rate; Subcooled water; Microcracks; Steam generator tubes; Back pressure;

    机译:泄漏流速;过冷水;微裂纹;蒸汽发生器管;背压;
  • 入库时间 2022-08-18 21:18:45

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