Design Verification for Control Logic in Nuclear Power Plant

2018 ◽  
Vol 4 (4) ◽  
Author(s):  
Hui Li ◽  
Guangxin Zhang

The control function for process, heating, ventilation, and air conditioning, and electrical systems in nuclear power plant (NPP) are represented by control logic diagram. To develop distributed control system (DCS), the designer and supplier should complete the activities of control logic configuration, testing, and verification, which are based on control logic diagram. Design verification is an effective method to ensure the correctness of control logic design. This paper represents a system, which is capable of implementing control logic design verification automatically for NPP instrumentation and control (I&C) system, as well as an overview of the procedure and some examples by using this system. With the design data (including control requirements and control logic diagrams in computer-readable format) and simulation technology, this system automatically performs design verification based on different rules and confirms the design outputs meet the inputs—the control requirements of plant's systems. Finally, a conclusion about the design verification system and future scenarios is given.

Author(s):  
Hui Li ◽  
Guangxin Zhang

The control function for process, HVAC and electrical systems in nuclear power plant (NPP) are represented by control logic diagram. To develop Distributed Control System (DCS), the designer and supplier should complete the activities of control logic configuration, testing and verification which are based on control logic diagram. Design Verification is an effective method to ensure the correctness of control logic design. This paper represents an overview of the procedure for control logic design verification in NPP I&C system, as well as the common function of platform/system to implement design verification. It focuses on the design verification for component control logic, to confirm the design outputs meet the inputs — the control requirements of plant’s systems. Finally, a conclusion about the design verification system as well as future scenarios is given.


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.


Author(s):  
Jean-Michel Palaric ◽  
Philippe Rebreyend ◽  
Philippe Mouly ◽  
Claude Esmenjaud ◽  
Frantisˇek Dalik

The modernization of the Dukovany nuclear power plant (four VVER 440 MWe reactor units owned by CˇEZ, the Czech national utility) is presented with a special focus on the digital safety instrumentation and control (I&C) system. The first Unit has been successfully modernized in compliance with the initial schedule. The following matters are further discussed in this paper: • Goal, scope and industrial organization of this modernization, • Main design criteria and I&C architecture, • Digital technologies in use, • Design and Licensing processes, • On-site installation strategy and main milestones, • Progress of work.


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

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