固态堆芯非对称热应力耦合试验研究

王严培; 唐昌兵; 李权; 李涛; 李晨曦; 秋博文; 范航; 李垣明

doi:10.13832/j.jnpe.2025.01.0152

固态堆芯非对称热应力耦合试验研究

doi: 10.13832/j.jnpe.2025.01.0152

1.
中国核动力研究设计院核反应堆技术全国重点实验室，成都，610213
2.
西南交通大学，成都，610031

基金项目: 四川省自然科学基金（2023NSFSC1316、2022NSFSC1953）；国家自然科学基金（12305195）

详细信息

作者简介:
王严培（1989—），男，博士，工程师，现主要从事燃料元件设计及性能分析方面的研究，E-mail: yanpei_wang@foxmail.com

中图分类号: TL334
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- 文章访问数: 16
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- PDF下载量: 3
- 被引次数: 0
出版历程
- 收稿日期: 2024-05-06
- 修回日期: 2024-07-02
- 刊出日期: 2025-02-15

Research on the Coupling Experiment of Asymmetric Thermal Stress in Solid Core

1.
National Key Laboratory of Nuclear Reactor Technology, Nuclear Power institute of China, Chengdu, 610213, China
2.
Southwest Jiaotong University, Chengdu, 610031, China

摘要

摘要: 非对称分布热应力耦合导致的燃料与基体相互作用是固态堆芯反应堆分析的关键问题，本研究采用数值模拟与试验相结合的方法，开发了分布式冷源和热源加载方式，对典型结构固态堆芯燃料元件开展了高温下热应力耦合模拟与试验研究。研究结果表明，试验测得的高温应变场与数值模拟结果较为接近，堆芯燃料基体在350℃温差下无失效风险，本研究建立的非对称分布式冷源和热源热应力耦合数值预测方法和试验技术能够用于固态堆芯反应堆非对称热应力分布研究，低温差下燃料元件基体无失效风险。
- 固态堆芯 /
- 非对称 /
- 热应力分布试验 /
- 数值模拟
Abstract: The interaction between fuel and matrix caused by asymmetric thermal stress coupling is a key problem in the analysis of solid-core reactor. In this study, a distributed cold source and heat source loading method is developed by combining numerical simulation with experiment, and the thermal stress coupling simulation and experimental study of typical solid-core reactor fuel elements at high temperature are carried out. The research results show that the high temperature strain field measured is close to the numerical simulation result, and there is no risk of failure of the core fuel matrix at 350°C. The numerical prediction method and experimental approach developed in this study for asymmetrically distributed cold and heat source thermal stress coupling can be applied to the analysis of asymmetric thermal stress distribution in solid cores, and there is no risk of failure of the fuel element matrix at low temperature difference.
- Solid core /
- Asymmetric /
- Thermal stress distribution test /
- Numerical simulation

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图 1 燃料设计示意图

Figure 1. Schematic Diagram of Fuel Design

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图 2 几何模型

其余未标注的圆形为热源

Figure 2. Geometric Model

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图 3 温度计算结果

Figure 3. Temperature Calculation Result

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图 4 热应力计算结果

Figure 4. Thermal Stress Calculation Result

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图 5 冷却方案设计

Figure 5. Design of Cooling Scheme

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图 6 热应力耦合试验装置

Figure 6. Thermal Stress Coupling Test Device

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图 7 热应力DIC测量

Figure 7. Thermal Stress DIC Measurement

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图 8 应变测量结果

Figure 8. Results of Strain Measurement

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图 9 微观检测

Figure 9. Microscopic Results

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图 10 温差200℃时数值模拟与试验获得的应变场分布规律对比

Figure 10. Comparison of Strain Field Distribution between Numerical Simulation and Experiment with a Temperature Difference of 200°C

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图 11 温差为350℃时堆芯变形放大50倍后的应力云图

Figure 11. Stress Contour of the Core Deformation with a Magnification of 50X and a Temperature Difference of 350°C

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表 1 堆芯结构最大应变

Table 1. Maximum Strain of Core Structure

温差/℃ 轴向应变/% 面内应变/%

50 1.31 1.29
100 1.50 1.58
250 1.70 1.98
350 1.95 2.35

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表 2 温差200℃时选取点的试验和数值模拟应变及误差

Table 2. Strains and Errors at Selected Points in Experiment and Numerical Simulation with a Temperature Difference of 200°C

数据点数值模拟应变/% 试验应变/% 误差/%

1 1.437 1.312 8.683
2 1.993 1.756 11.886
3 1.453 1.359 6.469
4 2.025 1.785 11.861
5 1.473 1.355 8.062
6 1.987 1.799 9.498

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