Study on Seismic Test of PWR Fuel Assembly
-
摘要: 燃料组件属I类抗震物项,其抗震问题直接关系核电厂运行安全,通常需通过抗震试验验证反应堆燃料组件抗震分析方法的合理性。本文模拟反应堆实际堆芯燃料组件安装方式,设计压水堆燃料组件抗震试验件与试验装置,针对不同组件数量布置方案,在高性能地震模拟振动台上开展试验研究。结果表明,水介质中燃料组件的第一阶频率为2.96 Hz,最大冲击力出现在燃料组件偏中间位置处,试验获取了地震作用下燃料组件的格架冲击力、格架相对位移、模拟堆芯板与围板的加速度等响应。试验结果可用于设计基准事故工况中燃料组件抗震分析模型的建立与分析软件的验证。Abstract: The seismic behavior of fuel assembly, as Class I seismic item, is directly related to the operation safety of nuclear power plants. It is usually necessary to verify the reasonableness of the seismic analysis method for reactor fuel assembly through seismic test. By simulating the actual reactor core fuel assembly installation method and designing the pressurized water reactor (PWR) fuel assembly seismic test specimens and devices, this paper carries out an experimental study for different fuel assembly quantity arrangement schemes on the high-performance seismic simulation vibration table. The results show that the first-order frequency of the fuel assembly in the water medium is 2.96 Hz, and the maximum impact force occurs in the position close to the middle of the fuel assembly. The lattice impact force and the relative displacement of the fuel assembly and the accelerations of the simulated core plate and baffle under the action of earthquake are obtained. The test results can be used to establish the seismic analysis model of fuel assembly and verify the analysis software under the designed reference accident condition.
-
Key words:
- Pressurized water reactor (PWR) /
- Fuel assembly /
- Seismic test /
- Lattice impact force
-
表 1 高性能振动台的主要技术指标
Table 1. Main Technical Indexes of High Performance Vibration Table
激振器数量 竖向 4 水平向 4 激振器型号 100-200-135P 150-300-220 动态激振力 ±195 kN×4
(竖向)±319 kN×2
(水平向)静态力 ±242 kN×4
(竖向)±397 kN×2
(水平向)设计负载与
最大加速度5 t(加速度峰值 5g)
10 t(加速度峰值 2g)台面尺寸 3 m×3 m g—重力加速度 表 2 冷态静水中主要工况表
Table 2. Main Working Conditions in Cold Still Water
组件排列 1×3 1×5 加速度幅值 0.25g 0.5g 0.25g 0.5g 时程数/条 10 10 10 10 -
[1] Nuclear Regulatory Commission. Standard Review Plan 4.2 Fuel System Design: NUREG-0800 Revision 3[S]. NRC, 2007: 29-32. [2] 国家能源局. 压水堆燃料组件及相关组件抗震设计规范: NB/T 20566—2019[S]. 北京: 中国原子能出版社, 2020: 2-3. [3] 刘刚,王丰,詹阳烈,等. 控制棒驱动机构抗震试验验收准则研究[J]. 核技术,2013, 36(4): 040607. [4] AKIYAMA H, WATABE M, SHIBATA H, et al. Proving test on the seismic reliability of nuclear power plant PWR reactor core internals[C]. SMiRT 10. Anaheim, CA, USA: IASMiRT, 1989: 859-864. [5] QUEVAL J C, BROC D, RIGAUDEAU J, et al. Seismic tests of interacting scale one fuel assemblies on shaking table[C]. SMiRT 16. Washington DC: IASMiRT, 2001. [6] VIALLET E, BOLSEE G, LADOUCEUR B, et al. Validation of PWR core seismic models with shaking table tests on interacting scale 1 Fuel assemblies[C]. SMiRT 17. Prague, Czech Republic: IASMiRT, 2003. [7] 谢永诚,姚伟达,姜南燕. 燃料组件在地震和失水工况下的结构动力反应分析[J]. 核动力工程,2002, 23(2): 139-147. [8] 张重珠,张忠岳. 燃料组件的地震和失水事故响应−FAMSAP程序的应用[J]. 原子能科学技术,1993, 27(4): 353-358. [9] 周云清,刘家正,朱丽兵. 地震加LOCA下的燃料组件安全分析研究[J]. 核动力工程,2011, 32(S1): 83-86. [10] 齐欢欢,吴万军,沈平川,等. 基于ANSYS的燃料组件事故动力分析程序[J]. 核动力工程,2018, 39(3): 40-44. doi: 10.13832/j.jnpe.2018.03.0040 [11] 国家核安全局. 核设备抗震鉴定试验指南: HAF•J0053[S]. 1995: 1-2. [12] VANMARCKE E H. Properties of spectral moments with applications to random vibration[J]. Journal of the Engineering Mechanics Division, 1972, 98(2): 425-446. doi: 10.1061/JMCEA3.0001593