压水堆燃料棒径向热膨胀建模方法及其影响分析研究

周雨锋; 谢伟戎; 万承辉; 曹新; 白家赫; 郭林

doi:10.13832/j.jnpe.2025.01.0030

压水堆燃料棒径向热膨胀建模方法及其影响分析研究

doi: 10.13832/j.jnpe.2025.01.0030

1.
西安交通大学核科学与技术学院，西安，710049
2.
台山核电合营有限公司，广东江门，529228

基金项目: 国家重点研发计划（2022YFB1902600）

详细信息

作者简介:
周雨锋（2000—），男，硕士研究生，现主要从事核反应堆物理计算方法研究，E-mail: 1552029917@qq.com

通讯作者:
万承辉，E-mail: wan.ch@mail.xjtu.edu.cn

中图分类号: TL334
计量
- 文章访问数: 9
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- PDF下载量: 5
- 被引次数: 0
出版历程
- 收稿日期: 2024-04-27
- 修回日期: 2024-06-11
- 刊出日期: 2025-02-15

Modeling Method and Impact Analysis of Fuel Rod Radial Thermal Expansion of PWR

1.
School of Nuclear Science and Technology, Xi’an Jiaotong University, Xi’an, 710049, China
2.
Taishan Nuclear Power Joint Venture Co., Ltd., Jiangmen, Guangdong, 529228, China

摘要

摘要: 在压水堆功率运行过程中，燃料芯块和燃料棒包壳由于温度变化会出现不同程度的热膨胀现象，对堆芯物理计算具有重要影响。为了在两步法计算流程中精确考虑燃料棒径向热膨胀对堆芯物理分析结果的影响，本文基于堆芯物理分析软件Bamboo-C提出了燃料棒径向热膨胀精确建模方法，分别在组件计算和堆芯计算层面对燃料棒径向热膨胀导致的几何变化予以考虑，且在堆芯计算层面通过温度场的迭代收敛最终确定精确的几何膨胀尺寸。本文以EPR1750机组为研究对象，对各燃料循环启动物理试验和功率运行过程进行计算，结果表明，与等温温度系数实测值的误差平均值由−3.065 pcm/K（1pcm=10^–5）降低至−1.870 pcm/K，与临界硼浓度实测值的误差平均值由−5.9ppm（1ppm=10^–6）、−5.7ppm降低至−2.5ppm、−2.7ppm。因此，本文提出的压水堆燃料棒径向热膨胀建模方法能够在一定程度上提高EPR1750机组关键安全参数的计算精度，具有一定的工程应用价值。
- 燃料棒径向热膨胀 /
- 温度系数 /
- 临界硼浓度 /
- Bamboo-C软件
Abstract: During the power operation of PWR, fuel pellets and cladding undergo varying degrees of thermal expansion due to temperature changes, which significantly impacts the core physics calculations. In order to accurately consider the influence of fuel rod radial thermal expansion on the core physics analysis results in the "two-step" scheme, this paper proposes a precise modeling method for fuel rod radial thermal expansion based on the reactor-physics analysis software Bamboo-C. This method considers the geometric changes caused by fuel rod radial thermal expansion at both the assembly calculation and reactor core calculation levels, and determines the precise geometric expansion size through iterative convergence of the temperature field at the core calculation level. In this paper, the EPR1750 unit is taken as the research object, and the startup physical tests and power operation processes of each fuel cycle are calculated. The results show that: the average error between the calculated and measured isothermal temperature coefficients decreased from −3.065 pcm/K (1pcm=10^–5) to −1.870 pcm/K, and the average error between the calculated and measured critical boron concentrations decreased from −5.9ppm (1ppm=10^–6) and −5.7ppm to −2.5ppm and −2.7ppm. Therefore, the PWR fuel rod thermal expansion modeling method proposed in this paper can improve the calculation accuracy of key safety parameters of EPR1750 to a certain extent and has certain engineering application value.
- Fuel rod radial thermal expansion /
- Temperature coefficient /
- Critical boron concentration /
- Bamboo-C software

HTML全文

图 1 压水堆燃料棒热膨胀建模方法流程

Figure 1. Calculation Process of Modeling Method for Fuel Rod Thermal Expansion of PWR

下载: 全尺寸图片幻灯片

图 2 特征线网格划分示意图

Figure 2. Schematic of MOC Grid Division

下载: 全尺寸图片幻灯片

图 3 U1C02b循环CBC计算值与实测值的误差

Figure 3. Error between Calculated and Measured Values of Critical Boron Concentration from U1C02b Cycle

下载: 全尺寸图片幻灯片

图 4 U2C02循环CBC计算值与实测值的误差

Figure 4. Error between Calculated and Measured Values of Critical Boron Concentration from U2C02 Cycle

下载: 全尺寸图片幻灯片

表 1 燃料组件k_eff的计算误差

Table 1. Calculation Error of k_eff of Fuel Assembly

分支计算工况	燃料棒自动热膨胀建模k_eff	输入卡片手动热膨胀建模k_eff	验证误差/ pcm
BC0-TM561.75	1.116729	1.116738	−0.9
BC0-TM585.25	1.106214	1.106215	−0.1
BC0-TM617.9	1.080652	1.080639	1.3
BC600-TM561.75	1.029785	1.029794	−0.9
BC600-TM617.9	1.014863	1.014851	1.2
BC1200-TM561.75	0.956858	0.956866	−0.8
BC1200-TM585.25	0.958293	0.958293	0
BC1200-TM617.9	0.957729	0.957717	1.2
BC2400-TM561.75	0.841334	0.841341	−0.7
BC2400-TM585.25	0.849296	0.849296	0
BC2400-TM617.9	0.863355	0.863345	1.0
TF561.75-TM561.75	1.040133	1.040142	−0.9
TF561.75-TM585.25	1.036904	1.036909	−0.5
TF561.75-TM617.9	1.026454	1.026458	−0.4
TF1500-TM561.75	1.003678	1.003684	−0.6
TF1500-TM585.25	0.999208	0.999208	0
TF1500-TM617.9	0.985902	0.985893	0.9

下载: 导出CSV

表 2 EPR1750机组多个循环ITC计算误差对比

Table 2. Comparison of ITC Calculation Errors for Multiple Cycles of EPR1750 Unit

机组循环	试验条件	原始模型计算误差/ (pcm·K⁻¹)	热膨胀模型计算误差/ (pcm·K⁻¹)
U1C01	ARO	−3.278	−2.584
	P1全插	−3.049	−2.343
	P1,P2全插	−2.853	−2.178
	P1,P2,P3全插	−2.961	−2.259
	P1,P2,P3,P4全插	−3.794	−3.091
U1C02	ARO	−3.845	−2.583
U1C02b	ARO	−0.801	0.996
U1C03	ARO	−2.824	−1.614
U2C01	ARO	−3.479	−2.125
	P1全插	−2.349	−0.998
	P1,P2全插	−3.373	−1.942
	P1,P2,P3全插	−3.511	−2.092
	P1,P2,P3,P4全插	−2.994	−1.516
U2C02	ARO	−3.598	−2.339
U2C03	ARO	−3.259	−1.387
ARO—控制棒全提条件；P1~P4—EPR1750机组的控制棒组代号

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