• ISSN 1673-5722
  • CN 11-5429/P

压水堆足尺燃料组件综合抗震试验系统研发与应用

张艳红 胡晓 朱洪东 邢国良 杨陈 高建勇

张艳红,胡晓,朱洪东,邢国良,杨陈,高建勇,2026. 压水堆足尺燃料组件综合抗震试验系统研发与应用. 震灾防御技术,21(3):1−10. doi:10.11899/zzfy20260079. doi: 10.11899/zzfy20260079
引用本文: 张艳红,胡晓,朱洪东,邢国良,杨陈,高建勇,2026. 压水堆足尺燃料组件综合抗震试验系统研发与应用. 震灾防御技术,21(3):1−10. doi:10.11899/zzfy20260079. doi: 10.11899/zzfy20260079
Zhang Yanhong, Hu Xiao, Zhu Hongdong, Xing Guoliang, Yang Chen, Gao Jianyong. Research and Application of a Comprehensive Seismic Test System for Full-scale PWR Fuel Assemblies[J]. Technology for Earthquake Disaster Prevention. doi: 10.11899/zzfy20260079
Citation: Zhang Yanhong, Hu Xiao, Zhu Hongdong, Xing Guoliang, Yang Chen, Gao Jianyong. Research and Application of a Comprehensive Seismic Test System for Full-scale PWR Fuel Assemblies[J]. Technology for Earthquake Disaster Prevention. doi: 10.11899/zzfy20260079

压水堆足尺燃料组件综合抗震试验系统研发与应用

doi: 10.11899/zzfy20260079
详细信息
    作者简介:

    张艳红,女,生于1970年。正高级工程师。主要从事工程抗震研究。E-mail:zhangyh@iwhr.com

  • 中图分类号: TL352;P315.9

Research and Application of a Comprehensive Seismic Test System for Full-scale PWR Fuel Assemblies

  • 摘要: 燃料组件的抗震安全性是核电厂安全评估的核心环节。当前,堆芯燃料组件的抗震安全验证多依赖于数值模拟,而模拟的精度和可靠性亟须足尺物理试验的验证。为准确标定自主化燃料组件的抗震分析模型参数、验证模型的合理性,并真实反映燃料组件在实际工况下的碰撞特性及高速轴向流场中的动态响应,本文自主研制了一套压水堆足尺燃料组件综合力学与抗震性能试验系统。该系统包含三大核心装置:空气环境足尺燃料组件跌落与多维力学性能试验装置、空气/静水环境足尺燃料组件综合力学性能测试与抗震试验装置,以及高速轴向流环境足尺燃料组件动态特性试验装置。本系统填补了国内同类大型物理试验的空白,不仅支持单组燃料组件的基础刚度(拉、压、弯、扭)与跌落试验,更具备灵活配置排组件数量、精细模拟组件间隙与板弹簧预紧力的能力,全面实现了空气、静水及变流速动水等复杂工况下燃料组件的抗震性能与极限抗震能力验证。该系统的成功研制,为我国自主化燃料组件抗震数值模型的参数标定与计算结果校验,以及组件实体的抗震安全裕度评估,提供了关键的技术支撑。
  • 图  1  足尺燃料组件跌落与多维力学性能试验装置与燃料组件示意图

    Figure  1.  Schematics of full-scale fuel assembly and its apparatus for drop and multi-dimensional mechanical property testing

    图  2  空气环境足尺燃料组件跌落试验

    Figure  2.  Drop test of full-scale fuel assembly in air

    图  3  空气环境足尺燃料组件拉压扭刚度试验

    Figure  3.  Tensile, compressive and torsional stiffness test of full-scale fuel assembly in air

    图  4  足尺燃料组件综合力学性能测试与抗震试验装置

    Figure  4.  Full-scale fuel assembly integrated mechanical property and seismic testing apparatus

    图  5  格架横向位移-横向拉力

    Figure  5.  Spacer grid lateral displacement - lateral force

    图  6  加卸载阶段格架的横向位移

    Figure  6.  Lateral displacements of grids during loading and unloading phases

    图  7  受拉定位格架的横向位移时程及各层格架的碰撞力时程

    Figure  7.  Time history of lateral displacement for the pulled grid and impact forces for grids at different levels

    图  8  燃料组件自由释放试验(20 mm幅值)

    Figure  8.  Free-release test of the fuel assembly in still water (20 mm amplitude)

    图  9  静水中燃料组件的前六阶振型

    Figure  9.  First six mode shapes of the fuel assembly in still water

    图  10  典型多频波作用下燃料组件的动态响应时程

    Figure  10.  Dynamic response time history of the fuel assembly under typical multi-frequency excitation

    图  11  典型地震波作用下燃料组件的动态响应时程

    Figure  11.  Dynamic response time history of the fuel assembly under typical seismic excitation

    图  12  高速轴向流环境足尺燃料组件动态特性试验装置

    Figure  12.  Full-scale fuel assembly dynamic characteristic testing apparatus under high-speed axial flow conditions

  • 郭严, 张国梁, 张艳红等, 2023. 压水堆燃料组件抗震试验研究. 核动力工程, 44(2): 109−115. doi: 10.13832/j.jnpe.2023.02.0109

    Guo Y., Zhang G. L., Zhang Y. H., et al., 2023. Study on seismic test of PWR fuel assembly. Nuclear Power Engineering, 44(2): 109−115. (in Chinese) doi: 10.13832/j.jnpe.2023.02.0109
    刘文进, 曾忠秀, 叶献辉等, 2013. 燃料组件由AFA 2G改为AFA 3G对反应堆堆内构件地震响应的影响. 核动力工程, 34(5): 25−29. doi: 10.3969/j.issn.0258-0926.2013.05.006

    Liu W. J., Zeng Z. X., Ye X. H., et al., 2013. Effect of fuel assembly when changing from AFA 2G to AFA 3G on seismic loads of reactor internal. Nuclear Power Engineering, 34(5): 25−29. (in Chinese) doi: 10.3969/j.issn.0258-0926.2013.05.006
    魏超, 宋辰宁, 郭超等, 2023. 堆芯燃料组件抗震计算关键参数的敏感性分析. 地震工程与工程振动, 43(5): 232−239. doi: 10.13197/j.eeed.2023.0523

    Wei C., Song C. N., Guo C., et al., 2023. Sensitivity analysis of key parameters in seismic calculation of core fuel assembly. Earthquake Engineering and Engineering Dynamics, 43(5): 232−239. (in Chinese) doi: 10.13197/j.eeed.2023.0523
    杨陈, 胡晓, 张艳红等, 2017-08-15. 乏燃料格架与组件地震试验时碰撞力测试方法: 中国, 107044895A.

    Yang C., Hu X., Zhang Y. H., et al., 2017-08-15. Collision force testing method for spent fuel screenwork and component seismic test: CN, 107044895A. (in Chinese)
    杨陈, 胡晓, 张艳红等, 2022-05-10. 一种测量核燃料组件非线性模态的装置: 中国, 216487337U.

    Yang C., Hu X., Zhang Y. H., et al., 2022-05-10. Device for measuring nonlinear mode of nuclear fuel assembly: CN, 216487337U. (in Chinese)
    张艳红, 胡晓, 高建勇等, 2021-11-16. 一种足尺燃料组件的抗震试验方法及抗震试验台架: 中国, 113654751A.

    Zhang Y. H., Hu X., Gao J. Y., et al., 2021-11-16. Full-scale fuel assembly anti-seismic test method and an anti-seismic test bed: CN, 113654751A. (in Chinese)
    张艳红, 胡晓, 郭严等, 2022a-08-30. 一种燃料组件格架等效碰撞试验方法及试验装置: 中国, 114974626A.

    Zhang Y. H., Hu X., Guo Y., et al., 2022a-08-30. Fuel assembly grillwork equivalent collision test method and test device: CN, 114974626A. (in Chinese)
    张艳红, 胡晓, 高建勇等, 2022b-11-01. 一种动水中足尺燃料组件动态特性试验装置及方法: 中国, 115265976A.

    Zhang Y. H., Hu X., Gao J. Y., et al., 2022b-11-01. Dynamic characteristic test device and method for full-scale fuel assembly in flowing water: CN, 115265976A. (in Chinese)
    周鼎, 黄聪彩, 李天勇等, 2025. 压水堆燃料组件定位格架动刚度估算及误差来源分析. 原子能科学技术, 59(3): 691−699. doi: 10.7538/yzk.2024.youxian.0909

    Zhou D., Huang C. C., Li T. Y., et al., 2025. Estimation of dynamic stiffness and analysis of error source of spacer grid for pressurized water reactor fuel assembly. Atomic Energy Science and Technology, 59(3): 691−699. (in Chinese) doi: 10.7538/yzk.2024.youxian.0909
    Capanna R., Ricciardi G., Sarrouy E., et al., 2022. Seismic response of cylinder assemblies in axial flow. Journal of Fluid Mechanics, 943: A15. doi: 10.1017/jfm.2022.433
    Drozdov Y. N., Tananov M. A., Osipova E. P., et al., 2012. Seismic tests of fuel assemblies. Russian Engineering Research, 32(3): 244−250.
    Faucher V., Ricciardi G., 2023. Adaptive time multiscale algorithms for fluid-structure interaction with impacts - Application to a row of PWR fuel assemblies under seismic loading. Annals of Nuclear Energy, 193: 110041. doi: 10.1016/j.anucene.2023.110041
    Ferrari G., Franchini G., Faedo L., et al., 2020. Nonlinear vibrations of a 3 × 3 reduced scale PWR fuel assembly supported by spacer grids. Nuclear Engineering and Design, 364: 110674. doi: 10.1016/j.nucengdes.2020.110674
    French Nuclear Safety Authority, 2020. Follow-Up to the French nuclear power plant stress tests - Closure report of the action plan of the French Nuclear Safety Authority (ASN). Montrouge: French Nuclear Safety Authority.
    Huang X., Cai F. C., Liu S., et al., 2021. Research on modal parameter identification of fuel assembly based on POD method. In: Proceedings of Pressure Vessels and Piping Conference. [2026-05-10]. https://doi.org/10.1115/PVP2021-61673
    IAEA, 2019. Design of the reactor core for nuclear power plants. Vienna: IAEA.
    IAEA, 2025. Structural behaviour of fuel assemblies in light water reactors. Vienna: IAEA.
    Jhung M. J., Choi Y., Oh C., 2022. Dynamic response of a fuel assembly for a KSNP design earthquake. Nuclear Engineering and Technology, 54(9): 3353−3360. doi: 10.1016/j.net.2022.03.027
    Park N., Kwon O., Yoo Y., et al., 2023. Experimental investigation of control rod drops into perturbed fuel assemblies. Journal of Nuclear Engineering and Radiation Science, 9(4): 041801. doi: 10.1115/1.4062275
    Pellissetti M., Kessler H., Schmidl J., et al., 2021. Seismic performance of fuel assemblies and impact force correlations with intensity-compatible sets of recorded ground motion time histories. Nuclear Engineering and Design, 375: 111052. doi: 10.1016/j.nucengdes.2021.111052
    Ricciardi G., Bellizzi S., Collard B., et al., 2009. Row of fuel assemblies analysis under seismic loading: modelling and experimental validation. Nuclear Engineering and Design, 239(12): 2692−2704. doi: 10.1016/j.nucengdes.2009.08.029
    Ricciardi G., 2016. Fluid–structure interaction modelling of a PWR fuel assembly subjected to axial flow. Journal of Fluids and Structures, 62: 156−171. doi: 10.1016/j.jfluidstructs.2016.01.006
    Ricciardi G., 2022. Analytical model of added mass, damping and stiffness of a fuel assembly induced by axial flow. Nuclear Engineering and Design, 389: 111670. doi: 10.1016/j.nucengdes.2022.111670
    Yamada T., Yoshimura S., Koide Y., et al., 2018. Verification and validation of dynamic response simulation codes for BWR fuel assemblies under seismic loading. International Journal of Pressure Vessels and Piping, 167: 25−31. doi: 10.1016/j.ijpvp.2018.10.005
    Yang C., Guo Y., Hu X., et al., 2023. A new experimental method for the nonlinear modal parameter identification of a pressurized water reactor fuel assembly. Science and Technology of Nuclear Installations, 2023: 8892196. doi: 10.1155/2023/8892196
  • 加载中
图(12)
计量
  • 文章访问数:  17
  • HTML全文浏览量:  23
  • PDF下载量:  11
  • 被引次数: 0
出版历程
  • 收稿日期:  2026-05-10
  • 录用日期:  2026-06-29
  • 修回日期:  2026-06-25
  • 网络出版日期:  2026-09-01

目录

    /

    返回文章
    返回