CIESC Journal ›› 2018, Vol. 69 ›› Issue (8): 3565-3576.DOI: 10.11949/j.issn.0438-1157.20180101

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Performance analysis of double-end self-pumping mechanical seal for main coolant pump of sodium-cooled fast reactor

CHEN Guoqi, SUN Jianjun, SUN Dianfeng, MA Chenbo   

  1. College of Mechanical and Electrical Engineering, Nanjing Forestry University, Nanjing 210037, Jiangsu, China
  • Received:2018-01-22 Revised:2018-03-25 Online:2018-08-05 Published:2018-08-05
  • Supported by:

    supported by the National Natural Science Foundation of China (51505230) and the China Postdoctoral Science Foundation (2017M611822)。

钠冷快堆核主泵用双端面自泵送机械密封性能分析

陈国旗, 孙见君, 孙电锋, 马晨波   

  1. 南京林业大学机械电子工程学院, 江苏 南京 210037
  • 通讯作者: 孙见君
  • 基金资助:

    国家自然科学基金项目(51505230);中国博士后基金项目(2017M611822)。

Abstract:

Sealing performance of reactor coolant pump is an important indicator for safety evaluation of sodium-cooled fast reactor. A double-end self-pumping mechanical seal was proposed for certain type of coolant pump for sodium-cooled fast reactor. Fluent numerical simulation at conditions of orthogonal design of experiments was performed to study influence of structural and operational parameters on open force and leakage rate of end surface. The pressure adjustment range of blocking fluid was analyzed to meet the requirement of zero argon leakage in the pump chamber. The results show that although both affect the open force within the experimental range of these parameters, the influence of ratio of groove to face width is more significant than that of helix angle. The open force was increased with the increase of ratio of groove over face width and helix angle. Also, the ratio of groove to face width had a significant effect on the leakage rate, which was increased rapidly with the increase of the ratio of groove to face width. The relationship between pressure of blocking fluid with both leakage rate and open force was obtained for conditions of maximum speed and shutdown. The mechanical seal is assured to be safe and effective at 0.05 MPa pump working pressure as long as blocking fluid pressure is controlled within 0.0528-1.6378 MPa.

Key words: reactor coolant pump, mechanical seal, CFD, orthogonal test, numerical simulation, optimization

摘要:

核主泵的密封性能是钠冷快堆安全评价的重要指标。以某型试验钠冷快堆核主泵为研究对象,提出了一种适用于钠冷快堆核主泵的双端面自泵送机械密封;运用正交试验法设计试验方案,并基于Fluent进行数值仿真模拟,探讨了该机械密封结构参数和工况参数对端面开启力和泄漏率的影响,分析了泵腔氩气零泄漏要求下的密封阻塞流体的压力调节范围。结果表明:在试验参数的范围内,槽面宽比和螺旋角对开启力均有影响,且槽面宽比影响更为显著,开启力随着槽面宽比和螺旋角的增大有上升的趋势;槽面宽比对泄漏率影响显著,泄漏率随槽面宽比的增大迅速增大。得到了最大转速和停机工况下阻塞流体压力与泄漏量、开启力的关系式;当泵腔工作压力为0.05 MPa时,只要阻塞流体压力不超出0.0528~1.6378 MPa区间均能保证密封安全有效。

关键词: 核主泵, 机械密封, 计算流体力学, 正交试验, 数值模拟, 优化

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