CFD-Based Pressurization Rate Optimization for Pressurized Water Reactor Containment Testing

XIANG Huawei; XIONG Bowei; RONG Hua; XU Jiehao; FAN Xinlang; GENG Yan

doi:10.3724/j.gyjzG24062106

Volume 55 Issue 8

Aug. 2025

Turn off MathJax

Article Contents

Article Navigation > INDUSTRIAL CONSTRUCTION > 2025 > 55(8): 193-199

XIANG Huawei, XIONG Bowei, RONG Hua, XU Jiehao, FAN Xinlang, GENG Yan. CFD-Based Pressurization Rate Optimization for Pressurized Water Reactor Containment Testing[J]. INDUSTRIAL CONSTRUCTION, 2025, 55(8): 193-199. doi: 10.3724/j.gyjzG24062106

Citation:

XIANG Huawei, XIONG Bowei, RONG Hua, XU Jiehao, FAN Xinlang, GENG Yan. CFD-Based Pressurization Rate Optimization for Pressurized Water Reactor Containment Testing[J]. INDUSTRIAL CONSTRUCTION, 2025, 55(8): 193-199. doi: 10.3724/j.gyjzG24062106

Citation:

PDF( 1091 KB)

CFD-Based Pressurization Rate Optimization for Pressurized Water Reactor Containment Testing

doi: 10.3724/j.gyjzG24062106

1. Central Research Institute of Building and Construction Co., Ltd., MCC Group, Beijing 100088, China;
2. Inspection and Certification Co., Ltd., MCC, Beijing 100088, China;
3. Fujian Ningde Nuclear Power Co., Ltd., Ningde 355200, China

Received Date: 2024-06-21
Available Online: 2025-10-24

Abstract

Abstract

The integrity test of the containment is one of the most crucial tests during the operation of nuclear power plants. To optimize and improve the pressurization rate for this test, the heat transfer mechanism of gas movement inside the containment during the experimental process was analyzed, and reasonable thermal boundary conditions for the gas were proposed. The computational fluid dynamics (CFD) method adopted used to establish a refined simulation analysis model for the fluid domain inside the containment. Historical data from the integrity test of the containment were employed to verify the reliability of the model. Based on the validated model, an analysis was conducted on the gas movement inside the containment after increasing the pressurization rate to 60 kPa/h. The results showed that the gas inside the containment flowed slowly, with a maximum average velocity of 0.165 m/s. The gas temperature exhibited a nonlinear change, rising by an average of 5.75℃. During pressurization, the gas pressure was uniformly distributed, and except for a range of 2 meters near the pressurization port, the pressure gradient in all other areas did not exceed 5 Pa. In summary, increasing the pressurization rate to 60 kPa/h caused only minor changes to the gas state inside the vessel.
- pressurized water reactor containment,
- integrity test,
- pressurization rate,
- gas state,
- CFD

FullText(HTML)

References(16)

References

[1]	杜宇, 刘勇, 丁小川. 福清核电厂1、2号机组安全壳整体泄漏率试验充压和降压速率优化的分析和研究[J]. 核科学与工程, 2017, 37(2): 199-202.
[2]	GHAVAMIAN S, COURTOIS A, VALFORT J L. Mechanical simulations of SANDIA Ⅱ tests OECD ISP 48 benchmark[J]. Nuclear Engineering and Design. 2007, 237(12/13): 1406-1418.
[3]	LABORATORIES S N. Overpressurization test of a 1: 4-scale prestressed concrete containment vessel model[R]. Washington: U. S. NRC, 2003.
[4]	ANDERSON P. Analytic study of the steel liner near the equipment hatch in a 1: 4 scale containment model[J]. Nuclear Engineering and Design. 2008, 238(7): 1641-1650.
[5]	周文权, 曲小朋, 孟凡彬. 核电站安全壳整体密封性试验方法[J]. 核动力工程, 1997(2): 58-62.
[6]	侍今奇. 重水堆安全壳整体密封性能测试技术研究[D]. 上海: 上海交通大学, 2007.
[7]	褚英杰, 欧阳钦. 安全壳整体泄漏率计算方法的比较分析[J]. 核动力工程, 2010, 31(6): 33-37.
[8]	黄海涛, 杨炯, 马先宏. 美国核电厂安全壳整体密封性试验[J]. 能源与节能, 2016(5): 85-87.
[9]	刘凯, 刘嘉兴, 徐海翔, 等. 国内外标准中预应力混凝土安全壳结构整体性试验的比较[J]. 工业建筑, 2021, 51(12): 1-6.
[10]	何锐, 贾武同, 赵健. 安全壳泄漏率测量仪表体积权重分配方法研究[J]. 核动力工程, 2015, 36(6): 101-104.
[11]	黄晓明, 李骏, 许国良, 等. 反应堆安全壳密封结构泄漏机理与预测模型的研究[J]. 核动力工程, 2016, 37(3): 116-121.
[12]	沈东明, 蔡建涛, 何锐, 等. 基于统计软件R的安全壳泄漏率试验数据有效性分析[J]. 核动力工程. 2020, 41(5): 99-103.
[13]	杨昕光, 宋翔, 单强, 等. 充压速率对安全壳内部气体稳定时间的影响性研究[J]. 工业建筑, 2021, 51(12): 68-73
[14]	王洪伟. 我所理解的流体力学[M]. 2版. 北京: 国防工业出版社, 2022.
[15]	王福军. 计算流体动力学分析: CFD软件原理与应用[M]. 北京: 清华大学出版社, 2004.
[16]	单建强. 压水堆核电厂系统与设备[M]. 西安: 西安交通大学出版社, 2021.