自然循环工况蒸汽发生器一回路流量分配特性分析

栾行健; 王文; 宋嘉豪; 韩菲; 蒋二辉; 程坤; 杨帆

doi:10.13832/j.jnpe.2024.04.0103

自然循环工况蒸汽发生器一回路流量分配特性分析

doi: 10.13832/j.jnpe.2024.04.0103

栾行健^1,,
王文^1, ,,
宋嘉豪¹,
韩菲¹,
蒋二辉¹,
程坤²,
杨帆²

1.
上海交通大学机械与动力工程学院，上海，200240
2.
中国核动力研究设计院核反应堆系统设计技术重点实验室，成都，610213

基金项目: 国家自然科学基金（12005215）

详细信息

作者简介:
栾行健（2000—），男，硕士研究生，现主要从事反应堆热工水力方面研究，E-mail: luanxingjian@sjtu.edu.cn

通讯作者:
王　文，E-mail: wenwang@sjtu.edu.cn

中图分类号: TL334
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- 文章访问数: 523
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- 被引次数: 0
出版历程
- 收稿日期: 2023-08-15
- 修回日期: 2023-11-12
- 刊出日期: 2024-08-12

Analysis on Flow Distribution Characteristics of Steam Generator under Natural Circulation Condition

1.
School of Mechanical Engineering, Shanghai Jiao Tong University, Shanghai, 200240, China
2.
Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu, 610213, China

摘要

摘要: 自然循环是核动力系统一种特殊运行工况，此时蒸汽发生器内倒U型管束会发生反流现象，从而影响一二次侧换热功率与运行稳定性。本研究开发核动力装置蒸汽发生器内一次侧流量分配计算程序，以芬兰PACTEL压水反应堆实验验证计算程序准确性，并讨论了回路质量流量、管高及一次侧入口温度对倒U型管束蒸汽发生器流量分配的影响。结果表明，倒U型管束的管高越低、一次侧入口温度越低会导致出现反流的临界压降和临界流速越小；相较于倒U型管高度的变化，蒸汽发生器一次侧入口温度的变化更加显著地影响倒U型管束的流量分配；增加循环质量流量可抑制反流现象，随着回路质量流量增加至某一阈值时，倒U型管束反流将不再出现。
- 蒸汽发生器 /
- 自然循环 /
- 反流 /
- 倒U型 /
- 流量分配
Abstract: Natural circulation is a particular operating condition of nuclear power system, and reversed flow occurs in the inverted U-shaped tube bundle of the steam generator, which affects the heat transfer between the primary and secondary sides and the operation stability. In this research, In this study, the calculation code of primary flow distribution in steam generator of nuclear power unit is developed, and the accuracy of the calculation code is verified by the Finnish PACTEL pressurized water reactor experiment. The effects of loop mass flow, tube height and primary inlet temperature on the flow distribution of inverted U-tube bundle steam generator are discussed. The results show that the lower the tube height and the lower the inlet temperature of the primary side of the inverted U-shaped tube bundle, the smaller the critical pressure drop and critical flow velocity will be. Compared with the change of the height of the inverted U-shaped tube, the change of the inlet temperature of steam generator primary side affects the flow distribution of the inverted U-shaped tube bundle more significantly. The reversed flow could be suppressed by increasing the circulation mass rate, and it will disappear when the mass rate increases to a threshold.
- Steam generator /
- Natural circulation /
- Reversed flow /
- Inverted U-shape /
- Flow distribution

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图 1 压降-流速特性曲线

Figure 1. Characteristic Curve between Pressure Drop and Velocity　　　　　

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图 2 流量分配迭代逻辑

Figure 2. Iterative Logic for Flow Distribution

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图 3 PWR PACTEL实验台架

Figure 3. PWR PACTEL Test Facility

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图 4 换热功率与压降随回路质量流量的变化

Figure 4. Heat Transfer and Pressure Drop Changing with Loop Mass Rate

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图 5 不同回路质量流量下各组单管流量分配情况

Figure 5. Single Tube Flow Distribution Changing with Loop Mass Rate

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图 6 换热功率与压降随高度变化

Figure 6. Heat Transfer and Pressure Drop Changing with Height　　　　　　

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图 7 不同管高度下各组单管流量分配情况

Figure 7. Single Tube Flow Distribution Changing with Height

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图 8 一次侧入口温度对换热功率与压降的影响

Figure 8. Heat Transfer and Pressure Drop Changing with Inlet Temperature of Primary Side

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图 9 不同温度下各组单管流量分配情况

Figure 9. Single Tube Flow Distribution Changing with Inlet Temperature of Primary Side

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表 1 各组倒U型换热管参数

Table 1. Parameters of Inverted U-shaped Tubes for Each Group

组号	管数	管长/mm	管高/mm	弯曲半径/mm
1	6	6186	3076	30.0
2	7	6229	3090	43.7
3	6	6518	3226	57.4
4	7	6561	3240	71.1
5	6	6850	3377	84.8
6	5	6893	3391	98.5
7	4	7180	3526	112.2
8	5	7224	3540	125.9
9	4	7511	3676	139.6
10	1	7554	3689	153.3

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表 2 计算值与实验值比较

Table 2. Calculated and Experimental Values

参数名	计算值	实验值	相对偏差/%
质量流量/(kg·s⁻¹)	1.16	1.11	4.5
蒸汽发生器两端压降/Pa	−244.6	−262.0	6.6
反应堆功率/kW	354.3	350	1.2

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表 3 流量分配计算结果

Table 3. Calculation Results of Flow Distribution

组号	流速/(m·s⁻¹)	质量流量/(kg·s⁻¹)
1	0.4051	0.3977
2	0.3991	0.4571
3	0.3683	0.3616
4	0.3560	0.4123
5	0.3063	0.3007
6	−0.2535	−0.2074
7	−0.2478	−0.1622
8	−0.2470	−0.2021
9	−0.2417	−0.1582
10	−0.2409	−0.0394

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参考文献(20)

[1]	SANDERS J. Stability of single-phase natural circulation with inverted U-tube steam generators[J]. Journal of Heat Transfer, 1988, 110(3): 735-742. doi: 10.1115/1.3250553
[2]	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 and Engineering, 1988, 99(4): 289-298. doi: 10.13182/NSE99-289
[3]	KIM J H, KIM T W, LEE S M, et al. Study on the natural circulation characteristics of the integral type reactor for vertical and inclined conditions[J]. Nuclear Engineering and Design, 2001, 207(1): 21-31. doi: 10.1016/S0029-5493(00)00417-9
[4]	章德,陈文振,王少明. 管长对立式倒U型管蒸汽发生器流动不稳定性的影响分析[J]. 原子能科学技术,2011, 45(6): 667-671.
[5]	SHI W, YI F, ZHAO P C, et al. Flow distribution investigation and sensitive analyses on reverse flow in U-tubes of steam generator under natural circulation[J]. Annals of Nuclear Energy, 2021, 154: 108112. doi: 10.1016/j.anucene.2020.108112
[6]	王一浒,卢川,丛腾龙,等. 自然循环U型管蒸汽发生器管内倒流受管长影响的理论研究[J]. 核动力工程,2021, 42(1): 23-27.
[7]	LI X J, CONG T L, CHEN Y R, et al. Research on backflow characteristics in U-tube of forced circulation steam generator under ocean conditions[J]. Progress in Nuclear Energy, 2021, 140: 103894. doi: 10.1016/j.pnucene.2021.103894
[8]	LI M R, HAO J L, CHEN W Z, et al. Experimental and theoretical investigations on reverse flow characteristics in vertically inverted U-tube steam generator under transient condition[J]. Progress in Nuclear Energy, 2020, 120: 103216. doi: 10.1016/j.pnucene.2019.103216
[9]	刘浩,马在勇,姜张锐,等. 不同参数对U型管式蒸汽发生器倒流影响的实验研究[J]. 原子能科学技术,2021, 55(7): 1309-1315. doi: 10.7538/yzk.2020.youxian.0543
[10]	唐瑜,徐建军,谢添舟,等. 自然循环条件下蒸汽发生器U型传热管倒流分布特性的实验研究[J]. 核动力工程,2018, 39(4): 43-47.
[11]	赵鹏程,衣峰,余红星,等. 自然循环条件下蒸汽发生器倒U型管流量分配特性研究[J]. 核动力工程,2021, 42(1): 192-197.
[12]	HAO J L, MA J J, HUANG Y P, et al. The reverse flow among parallel U-tubes in steam generator under natural circulation condition: a review[J]. Annals of Nuclear Energy, 2023, 191: 109908. doi: 10.1016/j.anucene.2023.109908
[13]	HAO J L, LI M R, CHEN W Z, et al. Theoretical investigation on the solution of the single-phase flow instability among parallel U-tubes[J]. Annals of Nuclear Energy, 2021, 160: 108406. doi: 10.1016/j.anucene.2021.108406
[14]	XU Z G, JI H R, HONG G, et al. Investigation on the role of mass flow rate in UTSG reverse flow under natural circulation condition[J]. Annals of Nuclear Energy, 2019, 132: 763-772. doi: 10.1016/j.anucene.2019.07.008
[15]	徐志刚,洪钢,郭奇勋,等. 自然循环工况下倒U型管蒸汽发生器管内倒流的数值计算分析[J]. 厦门大学学报: 自然科学版,2017, 56(6): 831-837.
[16]	张锐,吴奇,马在勇,等. 低流量单相工况下倒U型管蒸汽发生器内倒流现象的数值模拟研究[J]. 核动力工程,2022, 43(S2): 33-39.
[17]	郝老迷. 核反应堆热工水力学[M]. 北京: 原子能出版社,2010: 166-169.
[18]	TALUKDER H U, BHUYAN M F R. Modelling of the PACTEL SBL-50 transient using RELAP5 computer code[R]. Göteborg: Chalmers University of Technology, 2012: 23-48.
[19]	TUUNANEN J, KOUHIA J, PURHONEN H, et al. General description of the PACTEL test facility[R]. Espoo: VTT Technical Research Centre of Finland, 1998.
[20]	KAUPPINEN O P, RIIKONEN V, KOUHIA V, et al. Analysis of reverse flow in low-rise inverted U-tube steam generator of PWR PACTEL facility[C]//Proceedings of International Topical Meeting on Nuclear Reactor Thermal Hydraulics. Chicago: ANS, 2015: 5044-5047.