核反应堆堆芯三维跨尺度多物理场耦合分析程序CorTAF开发进展

苏光辉; 董正阳; 刘凯; 王明军; 田文喜; 秋穗正

doi:10.13832/j.jnpe.2025.05.0206

核反应堆堆芯三维跨尺度多物理场耦合分析程序CorTAF开发进展

doi: 10.13832/j.jnpe.2025.05.0206

苏光辉^{1, 2,},
董正阳^{1, 2},
刘凯^{1, 2},
王明军^{1, 2},
田文喜^{1, 2},
秋穗正^{1, 2}

1.
西安交通大学核科学与技术学院，西安，710049
2.
陕西省先进核能技术重点实验室，西安，710049

基金项目: 中核集团领创科研项目基金；中核集团青年英才项目

详细信息

作者简介:
苏光辉（1966—），男，教授，现主要从事核动力系统热工安全及相关领域研究，E-mail: ghsu@mail.xjtu.edu.cn

中图分类号: TL333
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- 文章访问数: 144
- HTML全文浏览量: 34
- PDF下载量: 22
- 被引次数: 0
出版历程
- 收稿日期: 2025-05-09
- 修回日期: 2025-05-27
- 网络出版日期: 2025-05-15
- 刊出日期: 2025-08-15

Development Progress of CorTAF: A Three-Dimensional Cross-Scale Multi-Physics Coupling Analysis Code for Nuclear Reactor Core

Su Guanghui^{1, 2
,},
Dong Zhengyang^{1, 2},
Liu Kai^{1, 2},
Wang Mingjun^{1, 2},
Tian Wenxi^{1, 2},
Qiu Suizheng^{1, 2}

1.
School of Nuclear Science and Technology, Xi’an Jiaotong University, Xi’an, 710049, China
2.
Shaanxi Key Laboratory of Advanced Nuclear Energy and Technology, Xi’an, 710049, China

摘要

摘要: 核反应堆堆芯作为核动力系统关键设备，其几何结构复杂，且不同物理场间存在强烈耦合作用。堆芯高精度精细化热工水力及多物理场耦合分析技术是先进核动力系统设计与安全分析的重要保证，西安交通大学核反应堆热工水力研究室（NuTHeL）构建了全堆芯核-热-流-沉积多物理场耦合分析模型，基于开源计算流体动力学（CFD）平台自主开发了通道级核反应堆堆芯三维跨尺度多物理场耦合分析程序CorTAF系列，实现了基于CFD方法的全压力容器内全尺寸多物理场的计算分析与预测，并开展了基于国际基准题的确认和验证（V&V）工作。近年来，研究团队基于上述研究基础不断开发与完善程序的数学物理模型，目前CorTAF程序已经具备了面向多种堆型（压水堆、铅铋堆、钠冷快堆等）、涵盖多种物理场（中子物理、热工水力、腐蚀沉积等）、串联多个系统（堆芯、上腔室、下腔室等）的跨尺度耦合计算能力。本文以压水堆CorTAF程序为例，介绍了其主要功能，总结回顾了相关工作，并提出了未来工作展望。
- CorTAF /
- 压水堆堆芯 /
- 通道级分辨率 /
- 多物理场耦合 /
- 压力容器跨尺度耦合
Abstract: The reactor core is a critical component of nuclear power systems with a complex geometric structure, and it experiences strong coupling effects between various physical fields. High-precision thermal-hydraulic and multi-physics coupling analysis of the core is essential for ensuring the design and safety analysis of advanced nuclear power systems. The Nuclear Reactor Thermal-Hydraulic Laboratory (NuTHeL) at Xi'an Jiaotong University has built a core-heat-flow-deposition multi-physics coupling analysis model, and has independently developed the CorTAF Three-Dimensional Cross-Scale Multi-Physics Coupling Analysis Code for Nuclear Reactor Core, which allows CFD-based multi-physics calculations and predictions for the entire pressure vessel. Validation and verification work has also been conducted based on international benchmark problems. In recent years, the research team has continually developed and refined the mathematical and physical models of the code. Currently, the CorTAF code supports cross-scale coupling calculations for multiple reactor types (PWR, LFR, SFR), physical fields (Neutronics, Thermal hydraulic, Deposition), and system structures (Core, Lower plenum, Upper plenum). This paper reviews the development process of the CorTAF series codes, presents their main functions and applications in PWR calculation, summarizes the current computational results, and discusses the future direction of the program's development.
- CorTAF /
- Pressurized water reactor core /
- Channel level resolution /
- Multiphysics coupling /
- Cross scale coupling

HTML全文

图 1 压水堆CorTAF程序框架介绍

Figure 1. Introduction to the CorTAF-PWR Code Framework

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图 2 全堆芯热工水力场分布

Figure 2. Thermal-Hydraulic Field Distribution of the Full Reactor Core

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图 3 堆芯通道“pin-by-pin”级别热工水力参数分布

Figure 3. Pin-by-pin Level Distribution of Thermal-hydraulic Parameters in Reactor Core Channels

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图 4 堵塞工况热工水力场分布

Figure 4. Thermal-Hydraulic Field Distribution under Blocking Conditions

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图 5 堆芯两相热工水力场分布

Figure 5. Two-phase Thermal-hydraulic Field Distribution

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图 6 堆芯腐蚀沉积物分布

Figure 6. Distribution of Corrosion and Deposition Products in the Core

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图 7 核热耦合计算结果

Figure 7. Neutronic Thermal-hydraulic Coupling Result

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图 8 压力容器速度云图

Figure 8. Velocity Contours in Pressure Vessel

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图 9 堆芯热工水力场分布

Figure 9. Distribution of Thermal-Hydraulic Fields in Reactor Core

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表 1 燃料组件数值模拟计算

Table 1. Numerical Simulation of Fuel Assemblies

物理量	COBRA程序计算值	CorTAF程序计算值	相对误差/%
冷却剂平均温度/K	585.85	585.20	0.11
冷却剂出口温度/K	600.70	599.30	0.23
包壳平均温度/K	605.44	603.60	0.30
包壳最高温度/K	622.34	620.07	0.36
燃料平均温度/K	862.40	871.42	1.05
燃料最高温度/K	1024.12	1033.33	0.90

下载: 导出CSV

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