基于CFD的蒸汽发生器U型管内回流现象数值分析

详细信息    查看全文 | 推荐本文 |

英文篇名：Simulation of Reflux in U-Tube of Steam Generator Based on CFD Method 作者：隋增光 ; 杨军 ; 杨晔 ; 董世昌 ; 徐乐瑾 英文作者：Sui Zengguang;Yang Jun;Yang Ye;Dong Shichang;Xu Lejin;Department of Nuclear Engineering and Technology,School of Energy and Power Engineering,Huazhong University of Science and Technology; 关键词：U型管 ; 蒸汽发生器(SG) ; 自然循环 ; 回流 英文关键词：U-tubes;;Steam generator(SG);;Natural circulation SG;;Reflux 中文刊名：HDLG 英文刊名：Nuclear Power Engineering 机构：华中科技大学能源与动力工程学院核工程与核技术系; 出版日期：2019-04-15 出版单位：核动力工程 年：2019 期：v.40;No.233 基金：国家“千人计划”青年人才项目专项资金(0222120003;0214120048) 语种：中文; 页：HDLG201902004 页数：6 CN：02 ISSN：51-1158/TL 分类号：14-19

摘要

反应堆一回路系统在自然循环条件下,蒸汽发生器(SG)部分U型管内可能会出现回流现象,利用计算流体动力学(CFD)方法,对某非能动三代反应堆蒸汽发生器U型管内流体的流动传热特性进行数值模拟分析。选取6组不同管长的U型管,对比分析U型管内单相流体的流动传热特性。基于数值仿真结果,得出6组U型管质量流量-进出口压降曲线,幵分析了U型管长度和一次侧进口流体温度与二次侧壁面温度温差(ΔT)对流体回流的影响。研究结果表明,当ΔT一定时,随着进出口压降的降低,长管内更容易发生回流。当U型管长度一定时,ΔT越小越容易发生回流。
        Under the condition of natural circulation in reactor systems, reflux may occur at U-tubes of steam generator(SG). Taken a SG of a Generation III Pressurized Water Reactor(PWR) with passive safety systems as the prototype, the thermal-hydraulic characteristics of the SG reflux are investigated. In this paper, the SG U-tubes are divided into six groups according to their lengths, and the flow and heat transfer characteristics of single-phase fluid in the U-tubes are analyzed with(CFD) methodology. The trends of total pressure drop against mass flow rate are derived based on the simulation results. The effect of the U-tube length and the temperature difference between the primary side fluid and the secondary side wall(ΔT) on the reflux are discussed. It is shown that when ΔT is constant, the reflux occurs more often in the longer U-tubes. When the U-tubes length is constant, the smaller ΔT is, the more often reflux occurs.

引文

[1]KUKITA Y,NAKAMURA H,TASAKA K,et al.Nonuniform steam generator u-tube flow distribution during natural circulation tests in rosa-iv large scale test facility[J].Nuclear Science&Engineering the Journal of the American Nuclear Society,1988,99:4(4):289-298.
    [2]SCHULZ R R,CHAPMAN J C,KUKITA Y,et al.Single and two-Phase natural circulation in westinghouse pressurized water reactor simulators:phenomena,analysis and scaling[C].USA:ASME FED,1987.
    [3]SANDERS J.Stability of single-phase natural circulation with inverted u-tube steam generators[J].Journal of Heat Transfer,1987,110(3):735-742.
    [4]杨晔,隋增光,董世昌,等.自然循环蒸汽发生器比例分析.第十五届全国反应堆热工流体学术会议暨中核核反应堆热工水力技术重点实验室2017年学术会议[C].北京:中国核学会,2017.
    [5]JEONG J,HWANG M,LEE Y J,et al.Non-uniform flow distribution in the steam generator U-tubes of a pressurized water reactor plant during single and two-phase natural circulations[J].Nuclear Engineering and Design,2004,231(3):303-314.
    [6]张勇,宊小明,黄伟.低流量下蒸汽发生器一次侧流量分配研究[J].核动力工程,2009,30(s1):56-59.
    [7]王川,于雷.自然循环蒸汽发生器倒U型管内单相流体倒流特性研究[J].核动力工程,2011,32(01):58-62.
    [8]杨瑞昌,刘京宫,黄彦平,等.自然循环蒸汽发生器倒U型管内的倒流计算[J].核动力工程,2010,31(01):57-60.
    [9]HAO J,CHEN W,WANG S.Flow instability analysis of U-tubes in SG based on CFD method[J].Progress in Nuclear Energy,2014,70:134-139.
    [10]李鹏飞.精通CFD工程仿真与案例实战[M].北京人民邮电出版社,2011:163-172
    [11]王少明,郝建立,章德,等.低流量下蒸汽发生器倒U型管内流动传热的数值模拟[J].船舶力学,2016,7:799-804.
    [12]ABELLI I,ISHII M.Flow excursion instability in down-ward flow systems:Part I.Single-phase instability[J].Nuclear Engineering and Design,2001,206(1):91-96.
    [13]郝建立,陈文振,王少明.自然循环蒸汽发生器倒U型管内倒流现象影响因素研究[J].原子能科学技术,2013,47(1):65-69.
    [14]段军,周涛,张蕾,等.倒U型管蒸汽发生器自然循环回流特性研究[J].原子能科学技术,2013,05:735-739.