螺旋管式直流蒸汽发生器壳侧流场数值模拟方法研究

王聪; 张巍; 李净松; 乔鹏瑞; 施慧烈

doi:10.13832/j.jnpe.2021.04.0171

螺旋管式直流蒸汽发生器壳侧流场数值模拟方法研究

doi: 10.13832/j.jnpe.2021.04.0171

王聪^{1, 2,},
张巍^{1, 2},
李净松^{1, 2},
乔鹏瑞³,
施慧烈^{1, 2}

1.
中核武汉核电运行技术股份有限公司，武汉，430074
2.
核动力运行研究所，武汉，430074
3.
中国原子能科学研究院，北京，102413

基金项目: 快堆产业联盟创新基金（2019-kdlm-cxjj-003）；中核集团青年英才项目（CNPO-K200556）

详细信息

作者简介:
王　聪（1992—），男，工程师，现主要从事蒸汽发生器热工水力的研究，E-mail: wangcong01@cnnp.com.cn

中图分类号: TL331
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- 被引次数: 0
出版历程
- 收稿日期: 2020-09-22
- 修回日期: 2020-10-20
- 刊出日期: 2021-08-15

A Method Study of Numerical Simulation on Flow Field of Spiral Tube in Steam Generator Shell Side

Wang Cong^{1, 2
,},
Zhang Wei^{1, 2},
Li Jingsong^{1, 2},
Qiao Pengrui³,
Shi Huilie^{1, 2}

1.
China Nuclear Power Operation Technology Corporation, Wuhan, 430074, China
2.
Research Institute of Nuclear Power Operation, Wuhan, 430074, China
3.
China Institute of Atomic Energy, Beijing, 102413, China

摘要

摘要: 铅冷快堆（LFR）采用一体化堆芯设计方案，其中的直流蒸汽发生器（OTSG）多采用螺旋管式结构以使整体结构小型紧凑。为研究LFR中螺旋管式OTSG壳侧铅铋冷却剂的流动传热特性，利用FLUENT软件，采用一种分区段计算方法，通过管壁热流密度拟合公式对螺旋管式OTSG壳侧进行了三维数值模拟。最终验证了该分段计算方法的正确性，分析了OTSG壳侧铅铋冷却剂的流动传热特性，获得了其速度、温度以及压力场的计算数据，为下一步OTSG流致振动分析和高温应力计算提供了依据。
- 螺旋管 /
- 直流蒸汽发生器（OTSG） /
- 数值模拟
Abstract: The lead based fast reactors often use integrated core design scheme, due to its compact structure, and the helical coil tube type once-through steam generators (OTSG) have been utilized in various reactors. In order to study the flow and heat transfer characteristics of the lead bismuth eutectic based coolant in the shell side of the helical coil tube OTSG in lead based fast reactors, a section-by-section solution method is adopted, and the wall heat flux fitting formula is used to simulate the flow field of shell side, with the help of FLUENT software. Finally, the correctness of the section-by-section solution method is verified, the flow and heat transfer characteristics of the shell side are analyzed, and the calculation data of velocity, temperature and pressure field are obtained. Its results lay a foundation for the next step of steam generator flow induced vibration analysis and high temperature stress calculation.
- Helical coil tube /
- Once-through steam generator (OTSG) /
- Numerical simulation

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图 1 OTSG结构示意图

Figure 1. Scheme of Structure for OTSG

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图 2 入口几何建模示意图 mm

Figure 2. Scheme of Structure for Entrance

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图 3 分区段计算方法示意图 mm

Figure 3. Configuration of Section-by-Section Solution Method　　　　

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图 4 螺旋换热管束区网格划分示意图 mm

Figure 4. Mesh in Tube Area

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图 5 管壁热流密度沿轴向高度变化示意图

Figure 5. Diagram of Wall Heat Flux Changes along Axial Direction

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图 6 网格敏感性分析

Figure 6. Analysis of Mesh Sensibility

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图 7 分区段计算验证选择区段示意图

Figure 7. Diagram of Selected Area for Section-by-Section Solution Method

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图 8 2种计算方法的“入口区+过热区”速度场云图

Figure 8. Velocity Field between Two Calculation Methods of Entrance Section and Superheated Section

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图 9 2种计算方法的“入口区+过热区”温度场云图

Figure 9. Temperature Field between Two Calculation Methods of Entrance Section and Superheated Section

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图 10 蒸汽发生器壳侧整体流场分布云图

Figure 10. Cloud Picture of the Shell Side Flow Distribution of the OTSG

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参考文献(6)

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[2]	SUI Z, CUI B G, MA Y L. The dynamic mathematic simulation model of steam generator for HTR[C]//Proceeding of the 19th International Conference on Nuclear Engineering. Osaka, 2011.
[3]	ALEMBERTI A, CARLSSON J, MALAMBU E, et al. European lead fast reactor-ELSY[J]. Nuclear Engineering and Design, 2011, 241(9): 3470-3480. doi: 10.1016/j.nucengdes.2011.03.029
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[5]	CHENG X, TAK N I. Investigation on turbulent heat transfer to lead-bismuth eutectic flows in circular tubes for nuclear applications[J]. Nuclear Engineering and Design, 2006, 236(4): 385-393. doi: 10.1016/j.nucengdes.2005.09.006
[6]	Nuclear Energy Agency. Handbook on lead-bismuth eutectic alloy and lead properties, materials compatibility, thermal-hydraulics and technologies[M]. Issy-Les-Moulineaux: Nuclear Energy Agency, 2007: 129-130.