共查询到18条相似文献,搜索用时 448 毫秒
1.
2.
土壤-结构相互作用(SSI)会影响核电厂厂房的地震响应。本文充分考虑SSI效应的影响,对10 MW高温气冷堆(HTR-10)厂房在三向地震载荷下的响应进行了分析。建立了土壤-结构耦合有限元模型,通过构造人工边界实现对地震波在无限域内传播过程的模拟,并对模型的准确性进行了验证。利用该模型计算了HTR-10厂房的地震响应,并对不同楼层的反应谱计算结果进行了分析。对于水平向反应谱,各楼层的反应谱谱型类似,SSI影响规律基本一致。在竖直方向上,结构的响应特点与楼板自身的竖向频率特性有明显关系,不同楼板的响应差别较大。一般情况下,SSI效应对竖向响应有抑制作用,且随着楼层增加更为明显。当楼板与土壤的固有频率接近时,竖向响应与其他楼层相比会有显著放大。 相似文献
3.
利用人工地震波生成算法,探讨考虑土壤-结构相互作用的核电厂电气厂房地震响应动力分析模型和计算方法。通过比较楼层反应谱,研究岩土材料参数和载荷的不确定性对结构响应的影响。结果表明:岩土材料参数对核电厂电气厂房地震响应的影响更大,单一岩土材料参数下计算得到的拓宽后的楼层反应谱不能完全包络参数变化带来的地震响应差别。即使最终的反应谱大于或等于各种不同岩土参数下的楼层反应谱,仍有必要对不同岩土参数下的楼层反应谱做包络。 相似文献
4.
结合结构-地基动力相互作用数值分析的最新发展,在集总参数场地动力简化模型的框架内,提出了一种便于非均质场地条件采用的核电站厂房时频域动力分析的新模式。该模式利用谐响应法求解场地真实频域动阻抗曲线,利用混合变量模型保证频域动刚度的时域无损转换,实现楼层谱的全时域计算。最后,以某百万千万级核电站反应堆厂房的抗震分析为例,开展均质与非均质场地条件下动刚度及上部结构楼层谱计算的对比研究,验证了该分析方法的精度与应用效果。计算结果表明,比较均质场地条件,水平成层非均质场地条件下竖直方向楼层谱峰值有较大幅度改变,必须在核电抗震安全评价中加以重视。 相似文献
5.
考虑SSI效应的核电站厂房楼层反应谱对比分析 总被引:1,自引:0,他引:1
在集总参数表征的场地动阻抗框架内,国内外主要核电厂抗震设计规范均推荐单一常系数弹簧-阻尼器并联体系表征均质场地动力模型。结合土-结构相互作用数值分析的最新发展,本文以CPR1000型反应堆厂房的集中质量简化模型作为研究对象,基于ASCE4-98规范、RCC-G规范、集10参数等适用于均质场地的集总参数地基模型以及适用于非均质复杂场地的粘弹性人工边界场地模型,开展了直接法和阻抗子结构法两种时程分析方法的对比研究,并将得到的楼层加速度反应谱与SASSI程序计算结果进行对比,互相验证了不同地基动力数值模型以及计算方法的有效性,对于评价核电厂地基适应性具有一定的指导与参考意义。 相似文献
6.
大亚湾核电厂核反应堆厂房的抗震分析基本沿用法国M310型机组的标准分析方法(RCC—G),对于土-结构相互作用(SSI)效应的考虑,采用简化的阻抗函数法。本文拟采用新的相对精确的基于Green函数的三维连续半空间边界子结构法考虑地基岩土的作用,进行SSI耦合系统的地震响应分析计算,并将计算的楼层反应谱(FRS)同设计值进行比较,对设计方法及其结果的趋向性(偏于安全/或不安全)进行评估。结果表明,与基于三维连续半空间边界子结构法的计算结果相比较,电厂设计偏于安全。 相似文献
7.
8.
9.
核电站辅助厂房结构—地基土相互作用体系的地震响应 总被引:2,自引:0,他引:2
本文主要针对核电站工程中辅助厂房结构与地基土相互作用体系在地震荷载下的“平-扭”地震响应进行了分析。在假定核岛基础为明置基础和考虑在同一基础上有安全壳及另一个辅助厂房结构存在的条件下,建立了整个相互作用体系的运动方程。最后结合我国秦山核电厂辅助厂房结构进行了数值计算和分析。 相似文献
10.
11.
本文采用Abrahamson的空间相干性模型,并考虑基础埋置效应,针对硬岩、软土厂址对核电站构筑物开展空间相干性地震反应谱分析,评估其非一致性对于埋置部位的地震响应谱影响情况,并得出对于低频区段地面的空间非一致性影响反应谱程度与埋置面接近;而高频区段地面的空间非一致性影响反应谱程度比埋置面要大的结论。 相似文献
12.
13.
A practical method to calculate the elasto-plastic seismic response of structures considering the dynamic soil-structure interaction is presented. The substructure technique in the time domain is utilized in the proposed method. A simple soil spring system with the coupling effects which are usually evaluated by the impedance matrix is introduced to consider the soil-structure interaction for embedded structures. As a numerical example, the response of a BWR-MARK II type reactor building embedded in the layered soil is calculated. The accuracy of the present method is verified by comparing its numerical results with exact solutions. The nonlinear behavior and the soil-structure interaction effects on the response of the reactor building are also discussed in detail. It is concluded that the present method is effective for the seismic design considering both the material nonlinearity of the nuclear reactor building and the dynamic soil-structure interaction. 相似文献
14.
This paper presents an accurate three-dimensional seismic soil–structure interaction analysis for large structures. The method is applied to the fuel building in nuclear power plants. The analysis is performed numerically in the frequency domain and the responses are obtained by inverse Fourier transformation. The size of the structure matrices is reduced by transforming the equation of motion to the modal coordinate system. The soil is simulated as a layered media on top of viscoelastic half space. Soil impedance matrices are calculated from the principles of continuum mechanics and account for soil stiffness and energy dissipation. Effects of embedment on the field equations is incorporated through the scattering matrices or by simply scaling the soil impedance. Finite element methods are used to discretize the concrete foundation for the generation of the soil interaction matrices. Decoupling of the sloshing water in the spent fuel pools and the free-standing spent fuel racks is simulated. The input seismic motions are defined by three artificial time history accelerations. These input motions are generated to match the ground design basis response spectra and the target power spectral density function. The methods described in this paper can handle arbitrary foundation layouts, allows for large structural models, and accurately represents the soil impedance. Time history acceleration responses were subsequently used to generate floor response spectra at applicable damping values. 相似文献
15.
为得到适合特定核电厂所需要的反应谱,考虑具体的场地条件及地震动参数,采用随机模拟方法与概率危险性分析相结合的方式,建立了生成超越概率为10-4的一致危险性谱(UHS)的方法。为进一步研究核电结构的抗震性能及UHS在实际核电结构中的适用性,设计和制作了1∶20的核电厂房结构模型进行振动台试验,采用2条天然波及UHS、厂址谱(SL-2)、RG1.60谱所生成的人工波对结构的响应进行比对分析。结果表明,不同地震波对核电结构的响应有所差异,UHS生成的人工波对上部结构加速度放大效应以及位移影响较大,对应的楼层反应谱幅值相对其他反应谱较高,进行结构及设备抗震设计时应予以考虑。 相似文献
16.
17.
Chang Chen 《Nuclear Engineering and Design》1974,30(1):100-110
Some commonly encountered problems in the seismic resistant design of nuclear power plant facilities are discussed. The topics included here are ground input motions, local geology versus source mechanism and travel path, three components inputs, torsional responses, floor response spectra, seismic resistant design of heavy equipment, the application of component mode synthesis technique, seismic resistant design of piping systems, equipment qualification by testing, the effects of close modes, underground pipe design, and soil structure interaction. 相似文献
18.
Finite element modeling of the AP1000 nuclear island for seismic analyses at generic soil and rock sites 总被引:1,自引:0,他引:1
Leonardo Tun-Sanjur Richard S. Orr Sener Tinic Diego Pea Ruiz 《Nuclear Engineering and Design》2007,237(12-13):1474-1485
The AP1000 is a standard design developed by Westinghouse and its partners for an advanced nuclear power plant utilizing passive safety features. The design has been certified by the US Nuclear Regulatory Commission based on their review of seismic analyses at hard rock sites. The plant has five principal building structures: the nuclear island, the turbine building, the annex building, the diesel generator building and the radwaste building. The nuclear island consists of the containment building (the steel containment vessel and the containment internal structures), the shield building and the auxiliary building. These structures are founded on a common basemat and are collectively known as the nuclear island. This paper describes shell and stick finite element models used in fixed base dynamic analyses for the hard rock design certification using the general purpose finite element program ANSYS. It describes a coarser shell model developed for use in soil structure interaction (SSI) analyses. This model is developed in both ANSYS and the soil structure interaction (SSI) program SASSI. Results of the three types of models from ANSYS analyses are compared for a hard rock site. Results are also compared between the ANSYS and SASSI analyses for the same model. 相似文献