Floor response spectra analysis of a nuclear reactor considering uncertainties in soil parameters

Structures ◽  
2022 ◽  
Vol 37 ◽  
pp. 305-317
Author(s):  
Yicheng Liu ◽  
Xiao Wang ◽  
Xiaoyan Wang ◽  
Xiaochun Zhang ◽  
Wei Gong ◽  
...  
1983 ◽  
Vol 105 (1) ◽  
pp. 35-41
Author(s):  
M. J. Yan

A consistent technique is derived for generating floor response spectra for equipment in nuclear reactor systems using response spectral analysis. The use of this technique eliminates the requirement for a time history analysis. The technique is based on the dynamic theory of coupling the supporting building with a very light spring-mass system representing the equipment. The response of the spring-mass system in the coupled systems is the floor response spectrum at the spring-mass system frequency. Resonant and off-resonant cases are derived separately. This technique is more efficient in the use of computer time than the conventional time history techniques. Moreover, a more realistic response spectrum is generated by this technique.


2012 ◽  
Vol 569 ◽  
pp. 572-575
Author(s):  
Bang Hyun Cho ◽  
Hoon Hyung Jung ◽  
Jae Duk Hwang ◽  
Chae Sil Kim ◽  
Hun Oh Choi

Thermocouples used for temperature measurement in nuclear power plants should meet the seismic qualification regulations of -IEEE Std 323 and 344 so as to withstand big vibrations such as earthquakes. In this paper, we establish a model for the estimation of the structural integrity of the thermocouples that are used in nuclear reactor building models. We then review the need for seismic measure using modal analysis and the boundary condition. If the natural frequency is less than 33 Hz for the installation environment, response spectrum analysis was carried out taking into consideration the weight of this interpretation and that of the seismic load models in the input response curves (Floor Response Spectra) OBE (Operation Base Earthquake), and SSE (Safe Shutdown Earthquake). Finally, analytical estimation of the structural integrity of a thermocouple is performed by making a comparison of the maximum stress and the allowable stress.


Author(s):  
Nikita Chernukha

The article is about nuclear power plant (NPP) safety analysis in case of aircraft crash. Specifically, the article considers the following problems: inclusion of aircraft crash into NPP design bases regarding calculation of frequency of an aircraft crash into NPP; aspects of justification of loads on NPP structures, systems and components (SSCs) caused by mechanical action of a primary missile – aircraft fuselage impact. Probabilistic characteristics of such random parameters as frequency of aircraft crash and direction of aircraft trajectory are determined by the results of analysis of world statistics of aviation accidents. Method of calculation of aircraft crash frequency on structures, buildings and NPP as a whole is presented. It takes into account options of accidental and intentional aircraft crashes and various aircraft approach scenarios. Procedure of probabilistic justification of loads on civil structures under aircraft impact is described. The loads are specified so as not to exceed allowable value of failure probability of NPP as a whole. Calculation of failure frequency of civil structures of existing NPP is given as an example to show analysis in case of a crash of an aircraft heavier than considered in NPP design. Procedure of probabilistic justification of dynamic loads on NPP equipment in case of aircraft impact is described. Method of floor response spectra (FRS) calculation with the required non-exceedance probability is given. Probabilistically justified loads in case of intentional aircraft impact (act of terrorism) are also considered. Additionally it is presented how internal forces calculated with the use of FRS with the required non-exceedance probability can be summed to provide analysis of subsystems.


2020 ◽  
Vol 36 (2_suppl) ◽  
pp. 213-237
Author(s):  
Miguel A Jaimes ◽  
Adrián D García-Soto

This study presents an evaluation of floor acceleration demands for the design of rigid and flexible acceleration-sensitive nonstructural components in buildings, calculated using the most recent Mexico City seismic design provisions, released in 2017. This evaluation includes two approaches: (1) a simplified continuous elastic model and (2) using recordings from 10 instrumented buildings located in Mexico City. The study found that peak floor elastic acceleration demands imposed on rigid nonstructural components into buildings situated in Mexico City might reach values of 4.8 and 6.4 times the peak ground acceleration at rock and soft sites, respectively. The peak elastic acceleration demands imposed on flexible nonstructural components in all floors, estimated using floor response spectra, might be four times larger than the maximum acceleration of the floor at the point of support of the component for buildings located in rock and soft soil. Comparison of results from the two approaches with the current seismic design provisions revealed that the peak acceleration demands and floor response spectra computed with the current 2017 Mexico City seismic design provisions are, in general, adequate.


Author(s):  
Ming L. Wang

Abstract During strong ground motions, members of reinforced concrete structures undergo cyclic deformations and experience permanent damage. Members may lose their initial stiffness as well as strength. Recently, Los Alamos National Laboratory has performed experiments on scale models of shear wall structures subjected to recorded earthquake signals. In general, the results indicated that the measured structural stiffness decreased with increased levels of excitation in the linear response region. Furthermore, a significant reduction in strength as well as in stiffness was also observed in the inelastic range. Since the in-structure floor response spectra, which are used to design and qualify safety equipment, have been based on calculated structural stiffness and frequencies, it is possible that certain safety equipment could experience greater seismic loads than specified for qualification due to stiffness reduction. In this research, a hysteresis model based on the concept of accumulated damage has been developed to account for this stiffness degradation both in the linear and inelastic ranges. Single and three degrees of freedom seismic Category I structures were analyzed and compared with equivalent linear stiffness degradation models in terms of maximum displacement responses, permanent displacement, and floor response spectra. The results indicate significant differences in responses between the hysteresis model and equivalent linear stiffness degradation models. The hysteresis model is recommended in the analysis of reinforced concrete shear-wall structures to obtain the in-structure floor response spectra for equipment qualification. Results of both cumulative and one shot tests are compared.


Author(s):  
C. Adam ◽  
F. Ziegler

Abstract The influence of light-weight secondary structures on the dynamic response of earthquake excited hysteretically damped shear frames with various elastic and inelastic substructure properties is studied numerically. The numerical procedure used in this paper is based on an iterative synthesis, where interface conditions as well as inelastic deformations are treated as additional fictitious loads and their intensities are updated in an iterative process. Acceleration response spectra of shear frames as well as floor response spectra are generated for various modal primary to secondary mass ratios. Also spectra of the standard deviation of primary and secondary accelerations are computed. Results, efficiently derived by the proposed method, are set in contrast to those derived by decoupled analyses to estimate their capability with respect to hysteretic structural behavior.


Structures ◽  
2021 ◽  
Vol 34 ◽  
pp. 2476-2498
Author(s):  
André Furtado ◽  
Hugo Rodrigues ◽  
António Arêde

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