scholarly journals 601 Development for Scismic lsolation Engineering of Nuclear Power Plant (Part 1) : Tri-axial Shaking Table Test of the Scale-down Main Steam Piping Model

2013 ◽  
Vol 2013.21 (0) ◽  
pp. 35-36
Author(s):  
Teruyoshi OTOYO ◽  
Akihito OTANI ◽  
Keisuke SASAJIMA ◽  
Hideo HIRAI ◽  
Hirohide IIIZUMI ◽  
...  
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Shaking Table Test ◽  
Plant Part ◽  
Shaking Table ◽  
Scale Down ◽  
Main Steam

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.

scholarly journals 602 Development of Seismic Isolation Technology for Nuclear Power Plant (Part 2) : Component Test of Main Steam Crossover Piping

2013 ◽  
Vol 2013.21 (0) ◽  
pp. 37-38
Author(s):  
kotoyo Mizuno ◽  
Masakazu Jinbo ◽  
Hiromu Okamoto ◽  
Shinji Kosugi ◽  
Shinji Matsuoka ◽  
...  
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Seismic Isolation ◽  
Plant Part ◽  
Component Test ◽  
Main Steam

Study on Load Capacity of Main Steam Superpipe Nozzle Used in Nuclear Power Plant

2017 ◽  
Author(s):  
Zhou Gengyu ◽  
Liang Shuhua ◽  
Sun Lin ◽  
Lv Feng
Keyword(s):  
Finite Element ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Structural Integrity ◽  
Load Capacity ◽  
Operating Conditions ◽  
Integrity Assessment ◽  
Inner Radius ◽  
Main Steam

The main steam super pipe used in nuclear power plant is an important safety class2 component. There are several nozzles located on it and linked with main steam safety valves. In the past two decades, the hot extrusion forming technology has been widely used to manufacture the super pipe nozzles. Comparing with traditional insert weldolet, the wall thickness of the extruded nozzle is relative small, and the nozzle inner radius is hard to control precisely in the fabrication process. Due to high temperature working condition and complicated loading conditions, the load capacity of the super pipe extruded nozzle has become an issue of concern for manufacturers and users. This paper presents a structural integrity assessment of a super pipe extruded nozzle. The nozzle stresses due to internal pressure and external loads for different operating conditions are obtained by the three-dimensional finite element analysis. The extruded nozzle is evaluated against the RCCM code Subsection C3200 Service Levels O, B and D stress limits for design, upset and faulted conditions. A parametric sensitivity analysis of the extruded nozzle inner radius size is also carried out. In addition, in order to reduce the calculation effort, an efficient calculation method is developed by using the commercial finite element program ANSYS.

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