Research on Software Quality Evaluation Model of Instrument and Control System in Nuclear Power Plant

Author(s):  
Huan-Lin Chen ◽  
Jian-Qiu Zhou ◽  
Yan Li
Robotica ◽  
2020 ◽  
Vol 39 (1) ◽  
pp. 165-180
Author(s):  
Zhang Zhonglin ◽  
Fu Bin ◽  
Li Liquan ◽  
Yang Encheng

SUMMARYThe particularity of nuclear power plant environment requires that the nuclear power inspection robot must be remote control operation. The main purpose of the inspection robot is to carry out inspection, prevention, reporting, and safety emergency operation on the instruments, so as to provide guarantee for the safe operation of the nuclear power plant. Based on the representative configuration of nuclear power robot at home and abroad, this paper develops a small and lightweight nuclear power plant inspection robot, including walking mechanism, lifting mechanism, operating mechanism, image acquisition, information communication and control system, etc., to carry on the statics analysis to the key components of the inspection robot and verify that the stiffness and strength of the mechanical structure meet the requirements of lightweight design. Modal analysis is carried out to verify that the motor does not cause resonance when working. The kinematic model of the robot has been established and can provide the theoretical basis for the controller design. A hierarchical control system based on LabVIEW upper computer monitoring and control operation interface is established, which uses adaptive fuzzy Proportional Integral Derivative (PID) control to simulate the walking control, and then realizes the control of walking mechanism through software programming, and the adaptive fuzzy PID control has better effect than the conventional PID control. The S-type acceleration and deceleration algorithm is used to realize the accurate control of the position location of the lifting mechanism. Finally, combined with the experiment of 5MS robot comprehensive experimental platform, it is proved that the inspection robot can realize remote control function operation.


2020 ◽  
Vol 139 ◽  
pp. 107207
Author(s):  
Raj kamal Kaur ◽  
Lalit Kumar Singh ◽  
Aditya Khamparia

Author(s):  
Antonio Ciriello ◽  
Daniela Kohler ◽  
Terry Morton ◽  
Thomas Lang

The I & C (Instrumentation and Control) design of the CVCS (Chemical and Volume Control System) for the EPR™ nuclear power plant in Taishan (TSN NPP) is shortly introduced and the corresponding I & C module assignment procedure, according to the functional safety class principle, is described. An example of the I & C module assignment procedure is given for a control loop of the CVCS. In addition, the corresponding advantages and drawbacks are described and discussed. The approach described introduces a new method for the concerned I & C design by improving the interface between the system, process, and I & C engineering design. In fact, a fruitful collaboration was reached between the system and I & C design for the EPR™ project in Taishan, for the concerned interface.


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