Cr涂层锆包壳池式沸腾传热实验研究

曾谢虎; 陈志强; 文青龙; 杜强; 张瑞谦; 杜沛南

doi:10.13832/j.jnpe.2023.02.0091

Cr涂层锆包壳池式沸腾传热实验研究

doi: 10.13832/j.jnpe.2023.02.0091

曾谢虎^{1, 2,},
陈志强^{1, 3},
文青龙^{1, 2, ,},
杜强^{1, 2},
张瑞谦⁴,
杜沛南⁴

1.
重庆大学能源与动力工程学院核工程与技术系，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.
东方电气集团科学技术研究院有限公司，成都，611731
4.
中国核动力研究设计院，成都，610213

详细信息

作者简介:
曾谢虎（1998—），男，硕士研究生，现主要从事反应堆热工水力方面的研究，E-mail: 202010131106@cqu.edu.cn

通讯作者:
文青龙，E-mail: qlwen@cqu.edu.cn

中图分类号: TL334
计量
- 文章访问数: 129
- HTML全文浏览量: 26
- PDF下载量: 36
- 被引次数: 0
出版历程
- 收稿日期: 2022-04-17
- 修回日期: 2022-05-30
- 刊出日期: 2023-04-15

Experimental Study on Pool Boiling Heat Transfer of Cr-coated Zirconium Cladding

Zeng Xiehu^{1, 2
,},
Chen Zhiqiang^{1, 3},
Wen Qinglong^{1, 2
, ,},
Du Qiang^{1, 2},
Zhang Ruiqian⁴,
Du Peinan⁴

1.
Department of Nuclear Engineering and Technology, School of Energy and Power Engineering, Chongqing University, Chongqing, 400044, China
2.
Key Laboratory of Low-Grade Energy Utilization Technologies and Systems, Ministry of Education, Chongqing University, Chongqing, 400044, China
3.
DEC Academy of Science and Technology Co., Ltd., Chengdu, 611731, China
4.
Nuclear Power Institute of China, Chengdu, 610213, China

摘要

摘要: 铬（Cr）涂层锆合金包壳被认为是最有前途的耐事故燃料（ATF）包壳材料之一，这种材料的表面状态对传热性能的影响程度将极大地影响着涂层锆包壳的工艺优化方向。本文在常压下的Cr涂层锆合金包壳池式沸腾实验装置中对不同工艺方法下制备的Cr涂层锆合金包壳进行实验，研究了粗糙度等表面状态对传热的影响规律及其机制。结果表明，表面粗糙度的提高能降低汽化核心产生的条件，在相同壁面过热度下可显著强化传热。在本文研究参数范围内，随着传热表面粗糙度的提高，临界热流密度（CHF）相应地呈上升趋势，增加表面粗糙度能有效提高CHF值。在此基础上，本文还建立了粗糙度对传热系数影响的预测关系式。
- 耐事故燃料（ATF） /
- 铬（Cr）涂层锆合金包壳 /
- 粗糙度 /
- 沸腾曲线 /
- 临界热流密度
Abstract: Chromium (Cr) coated zirconium alloy cladding is considered as one of the most promising cladding materials for accident tolerant fuel (ATF). The degree of influence of the surface state of this material on the heat transfer performance will greatly affect the process optimization direction of coated zirconium cladding. In this paper, experiments are conducted on the Cr-coated zirconium alloy claddings prepared under atmospheric pressure in the pool boiling experimental device for Cr-coated zirconium alloy cladding. The influence law and mechanism of surface states such as roughness on heat transfer are studied. The results show that the improvement of surface roughness can reduce the conditions for the formation of vaporization core and significantly enhance heat transfer under the same wall superheat degree. Within the range of parameters studied in this paper, with the increase of heat transfer surface roughness, CHF shows an upward trend accordingly. Increasing the surface roughness can effectively improve the CHF value. On this basis, the prediction relational expression of the influence of roughness on heat transfer coefficient is also developed in this paper.
- Accident tolerant fuel (ATF) /
- Chromium (Cr) coated zirconium alloy cladding /
- Roughness /
- Boiling curve /
- Critical heat flux

HTML全文

图 1 实验段示意图

T1~T4—热电偶测点

Figure 1. Schematic Diagram of Experimental Section

下载: 全尺寸图片幻灯片

图 2 汽液边界识别

Figure 2. Vapor-liquid Boundary Identification

下载: 全尺寸图片幻灯片

图 3 图像边界法向量

Figure 3. Normal Vector of Image Boundary

下载: 全尺寸图片幻灯片

图 4 Cr涂层锆合金包壳池式沸腾曲线

Figure 4. Pool Boiling Curve of Cr-coated Zirconium Alloy Cladding

下载: 全尺寸图片幻灯片

图 5 接触角与表面粗糙度对比

Figure 5. Comparison of Contact Angle and Surface Roughness　　　　　　

下载: 全尺寸图片幻灯片

图 6 接触角与壁面过热度对比

Figure 6. Comparison of Contact Angle and Wall Superheat

下载: 全尺寸图片幻灯片

图 7 局部汽泡脱离

Figure 7. Local Bubble Detachment

下载: 全尺寸图片幻灯片

图 8 不同时刻的局部汽泡聚合

Figure 8. Local Bubble Polymerization at Different Times

下载: 全尺寸图片幻灯片

图 9 不同时刻的周期性汽膜

Figure 9. Periodic Vapor Film at Different Times

下载: 全尺寸图片幻灯片

图 10 Cr涂层锆合金包壳泡核沸腾区传热系数曲线

Figure 10. Heat Transfer Coefficient Curve in the Nucleate Boiling Area of Cr-coated Zirconium Alloy Cladding

下载: 全尺寸图片幻灯片

图 11 CHF发生时的汽膜图像

Figure 11. Vapor Film Image when CHF Occurs

下载: 全尺寸图片幻灯片

图 12 CHF与粗糙度对比

Figure 12. Comparison of CHF and Roughness

下载: 全尺寸图片幻灯片

图 13 CHF与接触角对比

Figure 13. Comparison of CHF and Contact Angle

下载: 全尺寸图片幻灯片

表 1 实验段主要参数

Table 1. Main Parameters of Experimental Section

参数名	参数值
实验段总长/mm	260
实验段被加热段长度/mm	100
实验段外径/mm	9.52
实验段壁厚/mm	0.58
氧化铝陶瓷层外径/mm	8.36
氧化铝陶瓷层内径/mm	6
导热铜片外径/mm	6
导热铜片通孔直径/mm	1
铜排截面积/mm²	400

下载: 导出CSV

表 2 Cr涂层锆合金包壳粗糙度

Table 2. Roughness of Cr-coated Zirconium Alloy Cladding

样件号	平均粗糙度/μm
B1	0.641
B2	0.443
B3	0.339
B4	0.355

下载: 导出CSV

表 3 直接测量参数不确定度

Table 3. Uncertainties of the Direct Measurement Parameters

测量参数	仪表精度	不确定度/%
温度	0.3℃	0.27
电流	1.0 A	0.14
电压	0.015 V	0.12

下载: 导出CSV

表 4 间接测量参数不确定度

Table 4. Uncertainties of the Indirect Measurement Parameters　　　　　　

测量参数	不确定度/%
包壳传热面积	0.1
实验段功率	0.18
表面热流密度	0.21
传热系数	4.6

下载: 导出CSV

表 5 核态沸腾起始点的壁面过热度和热流密度

Table 5. Wall Superheat and Heat Flux at Onset of Nucleate Boiling (ONB)

样件号	壁面过热度/℃	热流密度/(kW·m⁻²)
B1	0.820	5.070
B2	1.642	6.594
B3	1.859	6.752
B4	1.582	6.534

下载: 导出CSV

表 6 Cr涂层锆合金包壳CHF值

Table 6. CHF Value of Cr-coated Zirconium Cladding

样件号	CHF/(kW·m⁻²)
B1	914.722
B2	726.705
B3	647.189
B4	651.358

下载: 导出CSV

参考文献(5)

[1]	SON H H, SEO G H, JEONG U, et al. Capillary wicking effect of a Cr-sputtered superhydrophilic surface on enhancement of pool boiling critical heat flux[J]. International Journal of Heat and Mass Transfer, 2017, 113: 115-128. doi: 10.1016/j.ijheatmasstransfer.2017.05.055
[2]	SON H H, CHO Y S, KIM S J. Dynamic wetting characteristics attributable for pool boiling heat transfer of FeCrAl-and Cr-layered vertical tubes[C]//Transactions of the Korean Nuclear Society Spring Meeting. Korean Nuclear Society Jeju, Korea, 2017.
[3]	徐济鋆. 沸腾传热和气液两相流[M]. 北京: 原子能出版社, 1993: 241-271.
[4]	DANILOVA G, BEL'SKII V. Study of heat transfer on boiling of freon 113 and freon 12 on pipes of differing roughness[J]. Kholodil’naia Tekhnika, 1965, 4: 24-28.
[5]	RIBATSKI G, JABARDO J M S. Experimental study of nucleate boiling of halocarbon refrigerants on cylindrical surfaces[J]. International Journal of Heat and Mass Transfer, 2003, 46(23): 4439-4451. doi: 10.1016/S0017-9310(03)00252-7