Frequency Analysis of the Motor Control Centers in a Nuclear Power Plant Using Testing and Simulating Methods

2013 ◽  
Vol 479-480 ◽  
pp. 1045-1050
Author(s):  
Wei Ting Lin ◽  
Yuan Chieh Wu ◽  
Chin Cheng Huang
Keyword(s):  
Motor Control ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Shaking Table Test ◽  
Spectral Response ◽  
Shaking Table ◽  
Element Analysis ◽  
Control Center ◽  
Frequency Curves

This study is aim to evaluate the seismic response of the motor control center cabinet in a nuclear power plant using shaking table test and 3D finite element analysis method. Three typical types of motor control center cabinet were used in this study and frequency curves and spectral response acceleration were used as the indices of the dynamic response. The results indicated that the resonance frequency for X and Y direction is about 12 Hz and 15 Hz, respectively, which is verified by the numerical results. The frequencies curves and spectral response acceleration generated by numerical and experimental method were similar and well fitting. Although the numerical method obtained the conservative results, the model accurately represents the dynamic characteristics of the actual motor control center cabinet for seismic verification.

scholarly journals Seismic Performance of CAP1400 Nuclear Power Station considering Foundation Uplift

2018 ◽  
Vol 2018 ◽  
pp. 1-16 ◽  
Author(s):  
Ling-Yun Peng ◽  
Ying-Jie Kang ◽  
Zhen-Yun Tang ◽  
Hua-Ting Chen
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Seismic Performance ◽  
Nuclear Power ◽  
Shaking Table Test ◽  
Shaking Table ◽  
Test Model ◽  
Foundation Slab ◽  
Adjacent Structures ◽  
Design Requirements

Under earthquake action, the reinforced concrete structure at the edge of the CAP1400 nuclear power plant foundation slab will be uplifted. In order to determine the seismic performance of this structure, a 1 : 12 scale shaking table test model was fabricated using gypsum as simulated concrete in order to meet scaled design requirements. By testing this model, the seismic response of the structure with consideration of the foundation uplift was obtained. Numerical analyses of the test model and the prototype structure were conducted to gain a better understanding of the structural seismic performance. When subjected to earthquakes, the foundation slab of the nuclear power plant experiences a slight degree of uplift but remains in the elastic stage due to the weight of the structure above, which provides an antioverturning moment. The numerical simulation is in general agreement with the test results, suggesting numerical simulations could be accurately employed in place of physical tests. The superstructure displacement response was found not to affect the safety of adjacent structures, and the seismic performance of the structure was shown to meet the relevant design requirements, demonstrating that this approach to modelling can serve as a design basis for the CAP1400 nuclear power demonstration project.

Field Testing to Validate Models Used in Explaining a Piston Problem in a Large Diesel Engine

1993 ◽  
Vol 115 (4) ◽  
pp. 721-727 ◽  
Author(s):  
M. J. Graddage ◽  
F. J. Czysz ◽  
A. Killinger
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Electric Utility ◽  
Analytical Models ◽  
Recording Equipment ◽  
Element Analysis ◽  
Piston Skirt ◽  
Lubrication Conditions ◽  
Engine Start

Two crankcase explosions occurred within one month in diesel engines that drive large emergency generator sets at a nuclear power plant in Eastern Pennsylvania. As a result, the electric utility conducted an extensive investigation to determine the root cause(s) of the problem. Initial inspections confirmed that the crankcase explosions were the result of pistons and liners becoming overheated. The technical challenge was to establish why the pistons and liners were overheating when other engines of the same type did not appear to have the problem in the same duty. Analytical models of piston motion, engine start, and run thermodynamics, and a finite element analysis of piston distortion during engine start and load transients were developed. Preliminary work with these models predicted a feature of the piston design that could adversely affect lubrication conditions during a rapid start and load transient. Final input data to refine the models were needed and these were obtained from tests carried out on a similar diesel generator operated by a municipality in Iowa. This paper describes the successful accomplishment of the field tests using state-of-the-art instrumentation and recording equipment. It also shows how the modeling and test work identified wear at certain locations on the piston skirt as the origin of distress leading to the crankcase explosions. Unfavorable engine starting and loading conditions as well as less than desirable piston skirt-to-liner lubrication conditions in the engines at the nuclear power plant have been identified as the root causes and corrective action has been initiated.

scholarly journals An Investigation on a Quantitative Tomographic SHM Technique for a Containment Liner Plate in a Nuclear Power Plant with Guided Wave Mode Selection

Sensors ◽  
2019 ◽  
Vol 19 (12) ◽  
pp. 2819 ◽  
Author(s):  
Yonghee Lee ◽  
Younho Cho
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Elastic Wave ◽  
Nuclear Power ◽  
Guided Waves ◽  
Mode Selection ◽  
Wave Mode ◽  
Guided Wave ◽  
Element Analysis ◽  
Wave Tomography

The containment liner plate (CLP) in a nuclear power plant is the most critical part of the structure of a power plant, as it prevents the radioactive contamination of the surrounding area. This paper presents feasibility of structural health monitoring (SHM) and an elastic wave tomography method based on ultrasonic guided waves (GW), for evaluating the integrity of CLP. It aims to check the integrity for a dynamic response to a damaged isotropic structure. The proposed SHM technique relies on sensors and, therefore, it can be placed on the structure permanently and can monitor either passively or actively. For applying this method, a suitable guided wave mode tuning is required to verify wave propagation. A finite element analysis (FEA) is performed to figure out the suitable GW mode for a CLP by considering geometric and material condition. Furthermore, elastic wave tomography technique is modified to evaluate the CLP condition and its visualization. A modified reconstruction algorithm for the probabilistic inspection of damage tomography algorithm is used to quantify corrosion defects in the CLP. The location and shape of the wall-thinning defects are successfully obtained by using elastic GW based SHM. Making full use of verified GW mode to Omni-directional transducer, it can be expected to improve utilization of the SHM based evaluation technique for CLP.

Fragility of a Flood Defense Structure Subjected to Multi-Hazard Scenario

2016 ◽  
Author(s):  
Saran Srikanth Bodda ◽  
Harleen Kaur Sandhu ◽  
Abhinav Gupta
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Hurricane Sandy ◽  
Nuclear Plant ◽  
Gravity Dam ◽  
Concrete Gravity Dam ◽  
Element Analysis ◽  
Dam Foundation ◽  
Flood Defense

The March 2011 Fukushima Daiichi nuclear power plant disaster has highlighted the significance of maintaining the integrity of flood protection systems in the vicinity of a nuclear power plant. In the US, Oyster Creek nuclear plant was shut down when high storm surge during hurricane Sandy threatened its water intake and circulation systems. A gravity dam located upstream of a power plant can undergo seismic failure or flooding failure leading to flooding at the nuclear plant. In this paper, we present the results from a study on evaluating the fragilities for failure of a concrete gravity dam under both the flooding and the seismic events. Finite element analysis is used for modeling the seismic behavior as well as the seepage through foundation. A time-dependent analysis is considered to account for appropriate nonlinearities. Failure of dam foundation is characterized by rupture, and the failure of dam body is characterized by excessive deformation for the flooding and seismic loads respectively. The study presented in this paper has focused on a concrete gravity dam because of the need of validation of models which exist in prior studies only for concrete gravity dams. However, the concepts are directly applicable to any concrete flood defense structure.

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