铅铋快堆螺旋管直流蒸汽发生器热工水力特性数值研究

丁雪友; 陈志强; 文青龙; 阮神辉; 乔鹏瑞

doi:10.13832/j.jnpe.2021.04.0021

铅铋快堆螺旋管直流蒸汽发生器热工水力特性数值研究

doi: 10.13832/j.jnpe.2021.04.0021

丁雪友^1,,
陈志强¹,
文青龙^{1, 2, ,},
阮神辉¹,
乔鹏瑞³

1.
重庆大学能源与动力工程学院核能工程系，重庆，400044
2.
重庆大学低品位能源利用技术及系统教育部重点实验室，重庆，400044
3.
中国原子能科学研究院，北京，102413

基金项目: 国家科技重大专项大型先进压水堆及高温气冷堆核电站资助（2019ZX06005001）

详细信息

作者简介:
丁雪友（1994—），硕士研究生，现主要从事反应堆热工水力研究，E-mail: Xueyouding@outlook.com

通讯作者:
文青龙，E-mail: qlwen@cqu.edu.cn

中图分类号: TL353⁺.13
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出版历程
- 收稿日期: 2020-05-26
- 修回日期: 2021-02-26
- 刊出日期: 2021-08-15

Numerical Investigation on Thermal Hydraulics of Helical Coil Tube Once Through Steam Generator for LBE Fast Reactor

1.
Department of Nuclear Engineering, School of Energy and Power Engineering, Chongqing University, Chongqing, 400044, China
2.
Key Laboratory of Low Grade Energy Utilization Technologies and Systems, Chongqing University, Chongqing, 400044, China
3.
China Institute of Atom Energy, Beijing, 102413, China

摘要

摘要: 本研究以铅铋快堆螺旋管直流蒸汽发生器（HOTSG）设计结构为研究对象，采用精细网格与多孔介质相结合的物理建模方法，通过一次侧三维湍流计算与二次侧用户自定义函数（UDF）分区传热计算相耦合的手段，在FLUENT求解器中开展了蒸汽发生器的热工水力特性数值分析研究。研究表明：铅铋入口附近的流量分配孔和腔室对应的直管段区域出现铅铋流速峰值，径向最大速度为0.431 m/s；入口腔室至管束区位置受到阻力突变的影响，压力、横流速度、轴向速度变化较大；热工参数变化符合流动与传热机理，临界热流密度（CHF）点附近一二次侧温差最大为109.61 K，此处最大热流密度为323.55 kW/m²。该研究将为铅铋快堆HOTSG结构设计、流致振动及安全评价提供重要的参考。
- 铅铋快堆 /
- 螺旋管直流蒸汽发生器（HOTSG） /
- 数值分析 /
- 多孔介质 /
- 热工水力
Abstract: The design of Lead and Bismuth Eutectic (LBE) cooled fast reactor helical coil tube steam generator is modeled in this study. Physical modeling method is developed with the combination of fine grid blocks and porous medium. Through the coupling the primary three-dimensional turbulence calculation and the secondary side heat transfer based on UDF (User Defined Function) method, a numerical analysis of the thermal hydraulic characteristics of the steam generator is carried out in the FLUENT solver. The results show that: a. the flow distribution holes near LBE inlet and the straight tubes in the chamber have peaks in the flow rate of LBE, and the maximum radial velocity is 0.431 m/s, b. when LBE flows from the inlet chamber into the tube bundle, the pressure, cross flow and axial flow rates change rapidly because of resistance mutation, and c. the changing process of thermal hydraulic parameters confirms to the qualitative mechanism analysis results of flow and heat transfer. The maximum temperature difference between primary and secondary sides near the Critical Heat Flux (CHF) point is 109.61 K, and the maximum heat flux is 323.55 kW/m². This study will provide an important reference for HOTSG structure design, fluid-induced vibration and safety evaluation of lead-bismuth fast reactor.
- LBE fast reactor /
- Helical coil tube once through steam generator /
- Numerical investigation /
- Porous medium /
- Thermal-hydraulics

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图 1 铅铋快堆HOTSG几何结构

Figure 1. Geometry Structure of LBE Cooled Fast Reactor HOTSG　　　　

下载: 全尺寸图片幻灯片

图 2 入口腔室径向流速分布

Figure 2. Radial Velocity Distribution in Inlet Plenum

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图 3 管束区主流横流速度和横流能量分布

Figure 3. Bulk Flow Cross Velocity and Energy Distribution in Bundle Area

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图 4 管束区轴向速度和压力分布

Figure 4. Axial Velocity and Pressure Distribution in Bundle Area　　　　

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图 5 HOTSG一二次侧和壁面温度分布

Figure 5. Primary Side, Secondary Side and Wall Temperature Distribution of HOTSG

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表 1 网格数量和质量表

Table 1. Number and Quality of HOTSG Meshes

部件	网格数量/万	网格质量
铅铋入口腔室	298.31	0.79
流量分配罩	205.24	0.871
氩气腔室	286.68	0.83
管束区	50.84	0.795
二次侧下降段	49.19	0.945
蒸汽腔室	17.99	0.904
直管段	450.8	0.917
总计	1359.05	0.385
除0.385为最小正交质量外，其余质量均为平均质量。

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表 2 HOTSG额定工况参数

Table 2. Full Power State Parameters of HOTSG

参数	数值
一次侧压力/MPa	0.1
一次侧入口温度/℃	480
一次侧入口流量/(kg·s ⁻¹)	26.55
二次侧压力/MPa	14
二次侧入口温度/℃	270
二次侧入口流量/(kg·s ⁻¹)	0.289
管束区高度/m	0.7
管束区内/外壳径/m	0.081/0.162

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表 3 控制方程离散方法

Table 3. Discretization Methods of Governing Equations

离散项	离散格式
重力	基于最小二乘单元
压力	体强制加权
动量	二阶迎风格式
能量	二阶迎风格式
湍动能	二阶迎风格式
比耗散率	二阶迎风格式

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参考文献(11)

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