|
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.2023.02.0109Guo 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.0258-0926.2013.05.006Liu 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.2023.0523Wei 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.0909Zhou 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
|