Cr涂层锆合金包壳腐蚀模型研究

沈勇; 曾谢虎; 段振刚; 文青龙; 袁波; 何梁; 高士鑫

doi:10.13832/j.jnpe.2024.S1.0175

Cr涂层锆合金包壳腐蚀模型研究

doi: 10.13832/j.jnpe.2024.S1.0175

沈勇^{1, 2,},
曾谢虎^{1, 2},
段振刚^{1, 2, 3, ,},
文青龙^{1, 2, 3},
袁波^{1, 2},
何梁⁴,
高士鑫⁴

1.
重庆大学能源与动力工程学院，重庆，400044
2.
两江新能源（核能与动力）实验室，重庆，400044
3.
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
4.
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（52201091）

详细信息

作者简介:
沈　勇（1996—），男，硕士研究生，现主要从事核反应堆热工水力研究，E-mail: 2470898965@qq.com

通讯作者:
段振刚，E-mail: zgduan96@163.com

中图分类号: TL334
计量
- 文章访问数: 64
- HTML全文浏览量: 15
- PDF下载量: 18
- 被引次数: 0
出版历程
- 收稿日期: 2023-12-28
- 修回日期: 2024-05-25
- 刊出日期: 2024-06-15

Investigation on Corrosion Model of Cr-coated Zirconium Alloy Cladding

Shen Yong^{1, 2
,},
Zeng Xiehu^{1, 2},
Duan Zhengang^{1, 2, 3
, ,},
Wen Qinglong^{1, 2, 3},
Yuan Bo^{1, 2},
He Liang⁴,
Gao Shixin⁴

1.
School of Energy and Power Engineering, Chongqing University, Chongqing, 400044, China
2.
Liangjiang Laboratory for New Energy (Nuclear Energy and Power), Chongqing, 400044, China
3.
Key Laboratory of Low-grade Energy Utilization Technologies and Systems, Ministry of Education, Chongqing University, Chongqing, 400044, China
4.
Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu, 610213, China

摘要

摘要: 作为耐事故燃料（ATF）包壳候选材料之一，Cr涂层可显著提高锆合金包壳的抗腐蚀和抗氧化性能，有望延长服役寿期。为评估Cr涂层锆合金包壳腐蚀氧化行为，本文建立了Cr涂层锆合金包壳在压水堆正常运行工况下的腐蚀模型，并基于文献实验数据对模型进行了验证；基于该模型进行了热流密度和质量流速对Cr涂层锆合金包壳的腐蚀影响分析。结果表明腐蚀厚度随热流密度的增加而增加；此外，冷却剂质量流速的增加引起包壳壁温减小，最终导致包壳腐蚀厚度减小。
- 压水堆 /
- 耐事故燃料（ATF） /
- Cr涂层锆包壳 /
- 腐蚀模型
Abstract: As one of the candidate materials for accident tolerant fuel (ATF) cladding, Cr coating can significantly improve the corrosion resistance and oxidation resistance of zirconium alloy cladding, which is expected to prolong the service life. In order to evaluate the corrosion and oxidation behavior of Cr-coated zirconium alloy cladding, a corrosion model of Cr-coated zirconium alloy cladding under normal operating conditions of PWR was established in this paper, and the model was verified based on the experimental data in the literature. Based on this model, the effects of heat flux and mass flow rate on the corrosion of Cr-coated zirconium alloy cladding were analyzed. The results show that the corrosion thickness increases with the increase of heat flux. In addition, the increase of coolant mass flow rate leads to the decrease of cladding wall temperature, which eventually leads to the decrease of cladding corrosion thickness.
- Pressurized water reactor /
- ATF /
- Cr-coated zirconium cladding /
- Corrosion model

HTML全文

图 1 Cr涂层锆合金包壳水侧腐蚀物理过程

Figure 1. Water Side Physical Process of Cr-coated Zirconium Alloy Cladding

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图 2 不同网格数量下流体温度对比

Figure 2. Comparison of Fluid Temperature with Different Grid Numbers

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图 3 建模示意图

Figure 3. Modeling Diagram

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图 4 流体温度与壁面温度分布

Figure 4. Fluid Temperature and Wall Temperature Distribution

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图 5 Cr涂层锆合金腐蚀模型计算对比

Figure 5. Calculation and Comparison of Cr-coated Zirconium Alloy Corrosion Model

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图 6 不同热流密度对腐蚀厚度的影响

Figure 6. Effect of Different Heat Flux on the Corrosion Thickness

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图 7 不同冷却剂质量流速对腐蚀厚度的影响

Figure 7. Effect of Different Coolent Mass Flow Rates on the Corrosion Thickness

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表 1 输入参数汇总

Table 1. Summary of Input Parameters

参数	数值
入口压力/MPa	15.5
入口温度/℃	286.3
最大热流密度/(MW·m⁻²)	1.0
入口质量流速/(kg·m⁻²·s⁻¹)	3330
栅距/mm	12.6
长度/mm	3658
时间步长/d	1
总时长/d	500

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表 2 Cr涂层锆合金包壳腐蚀实验工况

Table 2. Corrosion Experimental Conditions of Cr-coated Zirconium Alloy Cladding

研究者	材料	热工条件	水化学条件	腐蚀时间/d
KREJČÍ	E110 （Cr涂层）	360℃	B:1050 mg/L K:15.9 mg/L Li:1 mg/L	225
Isabel	Zr-4 （Cr涂层）	18.7 MPa/360℃	Li:10 mg/L B:650 mg/L	60
Wei	Zr-4 （Cr涂层）	18.6 MPa/360℃	B:200 mg/L Li:1.2 mg/L	83

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参考文献(13)

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