Analyzing and Comparing the Floor Response Spectra of the NPP Based on Different Soil Dynamic Numerical Models

2013 ◽  
Author(s):  
Xiu-yun Zhu ◽  
Rong Pan
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Seismic Design ◽  
Nuclear Power ◽  
Numerical Models ◽  
Response Spectra ◽  
Site Conditions ◽  
Design Codes ◽  
Floor Response Spectra ◽  
Soil Dynamic

The traditional soil dynamic impedance models, recommended by the main international seismic design codes of the nuclear power plant (NPP), are only expressed by a single parallel connection system of spring and dashpot which can not reflect the dynamic stiffness varying with excitation frequencies, and also can not simulate the cases of non-homogeneous site conditions. With the recent development of soil-structure interaction (SSI) analysis, based on the damping-solvent extraction method (DSEM) and the lumped parameter models recommended by seismic design codes of ASCE4-98,RCCG which are all applicable to the homogeneous site and also massless foundation model and viscous-spring artificial boundary model of especially fit for the numerical simulation of non-homogeneous site, comparative study of both the direct method and sub-structure method is carried out in this paper. Finally, by taking the analysis of floor response spectra (FRS) for a certain CPR1000 reactor building as an example, comparative analyses of homogeneous and layered site conditions using various soil dynamic numerical models above-mentioned are performed. In addition, in order to validate the accuracy, the calculated results are compared to that of SASSI program. The results show that FRS in the horizontal direction are good agreement regardless for the homogeneous and layered site conditions, the shapes of FRS in the vertical direction change obviously in the homogeneous site condition. This paper provides some guidance and reference in the aspect of evaluation the seismic suitability for the site of nuclear power plant (NPP).

Reanalysis of the floor response spectra of the Ignalina Nuclear Power Plant Reactor Building

2017 ◽  
Vol 324 ◽  
pp. 260-268
Author(s):  
Gintautas Dundulis ◽  
Rimantas Kačianauskas ◽  
Darius Markauskas ◽  
Eugeniuš Stupak ◽  
Stanislav Stupak ◽  
...  
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Response Spectra ◽  
Floor Response Spectra ◽  
Reactor Building ◽  
Plant Reactor

scholarly journals Dynamic seismic analysis of nuclear power plant buildings and bearing stratum

2021 ◽  
Vol 31 (4) ◽  
pp. 79-88
Author(s):  
S. V. Koval ◽  
A. V. Kuzminov ◽  
P. A. Rodin ◽  
N. M. Sidorov
Keyword(s):  
Power Plant ◽  
Nuclear Power ◽  
Seismic Analysis ◽  
Seismic Loading ◽  
Response Spectra ◽  
Kinematic Parameters ◽  
Specialized Software ◽  
Floor Response Spectra ◽  
Calculation Results ◽  
Supporting Frame

Various approaches are used for simulating seismic loading and collaboration of a structure and a bearing stratum when carrying out dynamic seismic analysis in specialized software. In the present work, the kinematic parameters of various structures and bearing stratum were calculated using SCAD and STAR_T software. Seismic performance of a reference tower type supporting frame was calculated for 7 grade earthquake. As a result, the floor accelerograms were calculated, and the floor response spectra were built. The calculation results obtained by various methods and structure models were analyzed and compared.

Study on Piping Response Under Multiple Excitation: Part 2 — Validation for Multiple Excitation Analysis of Piping

2013 ◽  
Author(s):  
Satoru Kai ◽  
Tomoyoshi Watakabe ◽  
Naoaki Kaneko ◽  
Kunihiro Tochiki ◽  
Makoto Moriizumi ◽  
...  
Keyword(s):  
Seismic Response ◽  
Seismic Design ◽  
Nuclear Power ◽  
Response Spectrum ◽  
Time History ◽  
Response Spectra ◽  
Shaking Table ◽  
Response Analysis ◽  
Multiple Time ◽  
Floor Response Spectra

The piping in a nuclear power plant is laid across multiple floors of a single building or two buildings, which are supported at many points. As the piping is excited by multiple-inputs from the supporting points during an earthquake, seismic response analysis by multiple excitations is needed to obtain the exact seismic response of the piping. However, few experiments involving such multiple excitation have been performed to verify the validity of multiple excitation analysis. Therefore, analysis of the seismic design of piping in Japan is performed by the enveloped Floor Response Spectrum (FRS), which covers all floor response spectra at all supporting points. The piping response estimated by enveloped FRS is conservative in most cases compared with the actual seismic response by multiple excitations. To perform rational seismic design and evaluation, it is important to investigate the seismic response by multiple excitations and to verify the validity of the analytical method by multiple excitation test. This paper reports the validation results of the multiple-excitation analysis of piping compared with the results of the multiple excitations shaking test using triple uni-axial shaking table and a 3-dimensional piping model (89.1mm diameter and 5.5mm thickness). Three directional moments from the analysis and the shaking test were compared on the validation. As the result, it is confirmed that the analysis by multiple time history excitation corresponds with the test result.

The Durability Design of the Technical Specifications for Nuclear Building Concrete of ACP1000

2017 ◽  
Author(s):  
Chen Dan ◽  
Liu Yulin ◽  
Zhang Weiguo
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Raw Materials ◽  
Site Conditions ◽  
Third Generation ◽  
The Third ◽  
Technical Requirements ◽  
Durability Design ◽  
Materials Used

For the continuous improvement of nuclear power plants safety standards, the actual requirements of the plant’s long service life, and the diversification of the plant site conditions, the durability design of nuclear building concrete structure has attracted widespread attention gradually. ACP1000, the third generation class nuclear power plant, is developed by China independently, and it may locate in different site conditions. Taking an ACP1000 nuclear power plant under construction as an example, this paper provides the technical requirements of concrete and concrete raw materials used in nuclear building. And by comparing with AP1000, the third generation class nuclear power plant imported from the United States, the advance and reasonableness of technical requirements of concrete and concrete raw materials used in nuclear building are provided further evidence.

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