Development of a Maintenance Optimization Procedure of Structural Components in Nuclear Power Plants

Author(s):  
Ph. Bryla ◽  
F. Ardorino ◽  
P. Aufort ◽  
J.P. Jacquot ◽  
L. Magne ◽  
...  
2015 ◽  
Vol 2015 ◽  
pp. 1-13 ◽  
Author(s):  
Ruifeng Yang ◽  
Jianshe Kang ◽  
Zhenya Quan

Nuclear power plants are highly complex systems and the issues related to their safety are of primary importance. Probabilistic safety assessment is regarded as the most widespread methodology for studying the safety of nuclear power plants. As maintenance is one of the most important factors for affecting the reliability and safety, an enhanced preventive maintenance optimization model based on a three-stage failure process is proposed. Preventive maintenance is still a dominant maintenance policy due to its easy implementation. In order to correspond to the three-color scheme commonly used in practice, the lifetime of system before failure is divided into three stages, namely, normal, minor defective, and severe defective stages. When the minor defective stage is identified, two measures are considered for comparison: one is that halving the inspection interval only when the minor defective stage is identified at the first time; the other one is that if only identifying the minor defective stage, the subsequent inspection interval is halved. Maintenance is implemented immediately once the severe defective stage is identified. Minimizing the expected cost per unit time is our objective function to optimize the inspection interval. Finally, a numerical example is presented to illustrate the effectiveness of the proposed models.


2005 ◽  
Vol 17 (1/2) ◽  
pp. 68-69
Author(s):  
Takashi KASUYA ◽  
Tetsuya UCHIMOTO ◽  
Toshiyuki TAKAGI ◽  
Tetsuo SHOJI

2004 ◽  
Vol 2004.3 (0) ◽  
pp. 187-188
Author(s):  
Takashi KASUYA ◽  
Takeshi OKUYAMA ◽  
Hisashi ENDO ◽  
Tetsuya UCHIMOTO ◽  
Toshiyuki TAKAGI ◽  
...  

1991 ◽  
Vol 113 (3) ◽  
pp. 471-475
Author(s):  
K. P. Singh ◽  
A. I. Soler ◽  
S. Bhattacharya

A rational analysis technique to evaluate structural integrity of primary welds in free-standing structures in accordance with the ASME Code is presented. This paper is intended to fill the void in the ASME Code rules for analyzing welds under “faulted” (level D) conditions in nonlinear free-standing structural components used in safety-related applications in nuclear power plants.


Author(s):  
Wenzheng Zhang ◽  
Zhipeng Feng ◽  
Xi Lv ◽  
Furui Xiong ◽  
Haiyang Song

The research on the linear and nonlinear responses of the plant structures, especially with internal equipment, subjected to underwater shock load make great significance in assessing the shock resistance ability of submerged nuclear power plants. In this paper, an optimal design of a small-sized submerged vehicle with internal components has been carried out to enhance the shock resistance. The dynamic responses and deformation mode of the vehicle subjected to underwater shock wave are firstly analyzed to determine the weak parts. The incident wave induced by UNDEX is equivalently replaced by half-sine shock wave, as the calculation of fluid-structure interaction (FSI) in the optimization process is very complicated. Based on the constraint condition of invariant weight, an optimization procedure is established by means of the commercial finite element code and optimization method. Numerical simulation is carried out to validate the effective of the optimal procedure. Compared with the original one, the maximum Mises stress of the submerged vehicle decreased from 426MPa to 359MPa, approximately reducing by 15.73%. The optimal result can be used to redesign the submerged vehicle with internal components suffered from underwater shock loading, as well as to enhance the anti-shock capability of submerged nuclear power plants.


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