Modelling and analysis of software reliability in digital instrumentation and control system of nuclear power plant

2014 ◽  
Author(s):  
Chao Guo ◽  
Yu Liu ◽  
Duo Li
Keyword(s):  
Control System ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Software Reliability ◽  
Nuclear Power ◽  
Digital Instrumentation ◽  
And Control

Redundancy Design in the Digital Instrumentation and Control System Design of Nuclear Power Plant

2014 ◽  
Vol 687-691 ◽  
pp. 751-754 ◽  
Author(s):  
Hao Ran Li ◽  
Xu Hong Yang
Keyword(s):  
Control System ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
System Design ◽  
Nuclear Power ◽  
Control System Design ◽  
Important Thing ◽  
Digital Instrumentation ◽  
Redundancy Design ◽  
And Control

First of all, the most important thing in introducing the digitization to the instrumentation and control system of nuclear power plant is its reliability. Then, what needs to do is designing each part of the system combined with the digital characteristic. Only through the system design of redundancy and diversification can the system of instrumentation and control be secure to run.

Design and Function Realization of Nuclear Power Inspection Robot System

Robotica ◽  
2020 ◽  
Vol 39 (1) ◽  
pp. 165-180
Author(s):  
Zhang Zhonglin ◽  
Fu Bin ◽  
Li Liquan ◽  
Yang Encheng
Keyword(s):  
Control System ◽  
Remote Control ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Pid Control ◽  
Nuclear Power ◽  
Control Operation ◽  
Inspection Robot ◽  
Walking Mechanism ◽  
And Control

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.

Modeling uncertainty of instrument and control system of nuclear power plant

2020 ◽  
Vol 139 ◽  
pp. 107207
Author(s):  
Raj kamal Kaur ◽  
Lalit Kumar Singh ◽  
Aditya Khamparia
Keyword(s):  
Control System ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Modeling Uncertainty ◽  
And Control

Overview on the Design Approach for the CVCS I & C of the EPR™ Nuclear Power Plant in Taishan

2013 ◽  
Author(s):  
Antonio Ciriello ◽  
Daniela Kohler ◽  
Terry Morton ◽  
Thomas Lang
Keyword(s):  
Control System ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Engineering Design ◽  
Nuclear Power ◽  
Control Design ◽  
Volume Control ◽  
Functional Safety ◽  
Control Loop ◽  
And Control

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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