模化比例对反应堆整体水力特性影响的研究

彭帆; 卢冬华; 谢翀; 汪春宇; 顾汉洋; 洪荣坤; 苏前华

doi:10.13832/j.jnpe.2024.070067

模化比例对反应堆整体水力特性影响的研究

doi: 10.13832/j.jnpe.2024.070067

彭帆^{1, 2,},
卢冬华²,
谢翀^2, ,,
汪春宇²,
顾汉洋¹,
洪荣坤²,
苏前华²

1.
上海交通大学核科学与工程学院，上海，200240
2.
中广核研究院有限公司，广东深圳，518026

详细信息

作者简介:
彭　帆（1986—），女，博士研究生，主要研究方向为反应堆热工水力，E-mail: pengfan@sjtu.edu.cn

通讯作者:
谢　翀，E-mail: andy_xc@126.com

中图分类号: TL334
计量
- 文章访问数: 20
- HTML全文浏览量: 7
- PDF下载量: 0
- 被引次数: 0
出版历程
- 收稿日期: 2024-07-31
- 修回日期: 2024-11-21
- 刊出日期: 2025-08-15

Research on the Influence of Scaling Ratio on the Integral Hydraulic Characteristics of Reactor

1.
School of Nuclear Science and Engineering, Shanghai Jiao Tong University, Shanghai, 200240, China
2.
China Nuclear Power Technology Research Institute Co.,Ltd., Shenzhen, Guangdong, 518026, China

摘要

摘要: 为了研究模化比例对反应堆整体水力特性的影响，本文基于相似理论，根据几何相似和欧拉数（Eu）相似模化设计了1∶1、3∶5和1∶5比例的实验本体，并在三套比例的实验本体上开展了反应堆原型流速下的流量分配实验、下腔室交混特性实验和下腔室流场实验。对比研究结果发现，实验工况下各比例本体内的流动均已进入自模区，流场彼此相似。模化比例对堆芯入口处流量分配因子、交混系数以及下腔室流场的影响比较小，其中不同比例本体内流量分配因子差异小于0.02，交混系数差异小于0.1。本研究可为整体水力学比例模化方法失真度的评估提供依据，为反应堆热工水力设计和实验研究提供参考。
- 模化比例 /
- 流量分配 /
- 交混 /
- 流场
Abstract: In order to study the influence of scaling ratio on the integral hydraulic characteristics of the reactor, 1∶1, 3∶5, and 1∶5 scaled mock-ups are designed based on geometric similarity and Euler number similarity, and flow distribution test, lower plenum mixing characteristics test and lower plenum flow field tests are conducted on three scaled mock-ups at a velocity of reactor prototype in this paper. The comparative results reveal the flows in 1∶1, 3∶5, and 1∶5 scaled mock-ups have entered self-simulation region and the flow fields are similar to each other. The scaling ratio has little influence on the flow distribution factors, mixing coefficients and flow fields in lower plenum at inlet of reactor core. Specifically, the difference in flow distribution factors between different scaling ratio mock-ups is less than 0.02, and the difference in mixing coefficients is less than 0.1. This study can provide a basis for evaluating the distortion of hydraulic modeling method, as well as a reference for reactor thermal hydraulic design and experimental research.
- Scaling ratio /
- Flow distribution /
- Mixing /
- Flow field

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图 1 反应堆的片状实验模型示意图

Figure 1. Schematic Diagram of Reactor Sheet Experimental Model

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图 2 堆芯模拟体

Figure 2. Core Simulator

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图 3 堆芯模拟体阻力系数图

Figure 3. Resistance Coefficient of Core Simulator

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图 4 实验装置示意图

Figure 4. Schematic Diagram of Experimental Setup

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图 5 实验测量示意图

Figure 5. Schematic Diagram of Experimental Measurement

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图 6 堆芯入口处的流量分布（偏差带范围±0.02）

Figure 6. Flow Distribution at the Core Inlet (Deviation Band ±0.02)

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图 7 堆芯交混系数分布（偏差带范围±0.1）

Figure 7. Distribution of Core Mixing Coefficient (Deviation Band ±0.1)

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图 8 流场拍摄区域示意图

Figure 8. Schematic Diagram of Flow Field Shooting Area

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图 9 下腔室无量纲速度场

Figure 9. Dimensionless Velocity Field in the Lower Plenum

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图 10 下腔室流线图

Figure 10. Streamline Chart of the Lower Plenum

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表 1 实验模型参数

Table 1. Experimental Model Parameters

参数	1∶1模型	3∶5模型	1∶5模型
模型总高/mm	4010	2406	802
模型总宽/mm	2300	1380	460
入口流量/(m³·h⁻¹)	~1365	~492	~54.6
入口截面/(mm×mm)	265×215	159×129	53×43
入口管处Re/10⁵	10.2	6.1	2.0
流量分配器处Re/10⁵	3.2	1.9	0.6

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参考文献(19)

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