Design Verification for Control Logic in Nuclear Power Plant

2017 ◽  
Author(s):  
Hui Li ◽  
Guangxin Zhang
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Control Function ◽  
Logic Design ◽  
Design Verification ◽  
Control Logic ◽  
Electrical Systems ◽  
Logic Diagram ◽  
Platform System

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.

Design Verification for Control Logic in Nuclear Power Plant

2018 ◽  
Vol 4 (4) ◽  
Author(s):  
Hui Li ◽  
Guangxin Zhang
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Control Function ◽  
Logic Design ◽  
Design Verification ◽  
Control Logic ◽  
Design Data ◽  
Logic Diagram ◽  
And Control

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.

Nuclear Power Plant Design Verification Based on the Analyzer

2013 ◽  
Author(s):  
Hanlin Wang ◽  
Mingguang Zheng ◽  
Tunfeng Qi
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Design Verification ◽  
Plant Design ◽  
Improve Design ◽  
Verification Methods ◽  
Basic Concepts

In this paper, the current nuclear power plant (abbreviated as NPP) design verification methods are analyzed, and employing nuclear power plant design analyzer (abbreviated as NPPDA,) is proposed to improve design verification. The main points include: the basic concepts of NPPDA, a detailed discussion of the principles of how NPPDA could play a role in design verification, and extended considerations on application of NPPDA in NPP design verification.

Modeling and Simulation of Pressure Control Logic Module in Pressurizer of Nuclear Power Plant

2013 ◽  
Vol 860-863 ◽  
pp. 2409-2414
Author(s):  
Miao Lei Yu ◽  
Xian Ping Zhao ◽  
Yong Zhe Niu ◽  
Ping Yang
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Software Package ◽  
Nuclear Power ◽  
Pressure Control ◽  
Simulation Software ◽  
Control Logic ◽  
Simulation Test ◽  
Logic Module ◽  
Typical Test

In view of the simulation problems of pressure control logic module in PWR nuclear power plant, a complete simulation model has been designed by using simulation software package Simulink. Based on the simulation test of the typical test signal, the model is proved to be effective and correct.

System Simulation of Nuclear Power Plant by Coupling RELAP5 and Matlab/Simulink

2006 ◽  
Author(s):  
Meng Lin ◽  
Dong Hou ◽  
Zhihong Xu ◽  
Yanhua Yang ◽  
Ronghua Zhang
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
System Simulation ◽  
Protection System ◽  
Control Logic ◽  
Matlab Simulink ◽  
Analysis Experiment ◽  
Simulation Time ◽  
Relap5 Code

Since RELAP5 code has general and advanced features in thermal-hydraulic computation, it has been widely used in transient and accident safety analysis, experiment planning analysis, and system simulation, etc. So we wish to design, analyze, verify a new Instrumentation And Control (I&C) system of Nuclear Power Plant (NPP) based on the best-estimated code, and even develop our engineering simulator. But because of limited function of simulating control and protection system in RELAP5, it is necessary to expand the function for high efficient, accurate, flexible design and simulation of I&C system. Matlab/Simulink, a scientific computation software, just can compensate the limitation, which is a powerful tool in research and simulation of plant process control. The software is selected as I&C part to be coupled with RELAP5 code to realize system simulation of NPPs. There are two key techniques to be solved. One is the dynamic data exchange, by which Matlab/Simulink receives plant parameters and returns control results. Database is used to communicate the two codes. Accordingly, Dynamic Link Library (DLL) is applied to link database in RELAP5, while DLL and S-Function is applied in Matlab/Simulink. The other problem is synchronization between the two codes for ensuring consistency in global simulation time. Because Matlab/Simulink always computes faster than RELAP5, the simulation time is sent by RELAP5 and received by Matlab/Simulink. A time control subroutine is added into the simulation procedure of Matlab/Simulink to control its simulation advancement. Through these ways, Matlab/Simulink is dynamically coupled with RELAP5. Thus, in Matlab/Simulink, we can freely design control and protection logic of NPPs and test it with best-estimated plant model feedback. A test will be shown to illuminate that results of coupling calculation are nearly the same with one of single RELAP5 with control logic. In practice, a real Pressurized Water Reactor (PWR) is modeled by RELAP5 code, and its main control and protection system is duplicated by Matlab/Simulink. Some steady states and transients are calculated under control of these I&C systems, and the results are compared with the plant test curves. The application showed that it can do exact system simulation of NPPs by coupling RELAP5 and Matlab/Simulink. This paper will mainly focus on the coupling method, plant thermal-hydraulic model, main control logics, test and application results.

Application Research of Safety Control and Information Device Based on FirmSys Platform in ACPR1000 Nuclear Power Plant

2017 ◽  
Author(s):  
Li-Ling Zhu ◽  
Bin Wu ◽  
Gang Li ◽  
Yi-Qin Xie ◽  
Yong-Bin Sun
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Power Plants ◽  
Control Function ◽  
Data Communication ◽  
Display Device ◽  
Typical Application ◽  
Safety Control ◽  
Human System

Because of the rapid changes that are taking place in the digital computer and the graphic display technology employed in a modern human system interface, the use of integrated digital display devices to replace traditional instruments has become a new application tendency in nuclear power plant. The safety control and display device (refer as to SCID hereafter) is a safety class digital Human System Interface (HSI) device of FirmSys platform. It provides display and control function of the safety system in ACPR1000 nuclear power plant. This paper mainly introduces the typical application architecture of SCID in ACPR1000 NPP, the main functions (including control and display function, application mode management function, data processing function and data communication function) of SICD and the innovation and improvement of SCID. The application of SCID has improved the integration of the HMI system and reduced the workload of the operating staff. It has been successfully applied in several ACPR1000 nuclear power plants.

Application of Virtual Reality Technology in Nuclear Power Plant Control Room Simulator

2018 ◽  
Author(s):  
Li Xiyun ◽  
Wang Xi ◽  
Liang Chenchen ◽  
Wang Shaohua
Keyword(s):  
Virtual Reality ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Design Verification ◽  
Control Room ◽  
Virtual Reality Technology ◽  
Operator Training ◽  
Machine Interface ◽  
And Function

Main control room simulator is widely used in design verification and operator training for nuclear power plant. The simulator needs to implement the arrangement, environment, human machine interface and function of main control room, which should be the same as much as possible. For designer, each type of reactor needs an individual simulator for design verification. As the number of unit increased, the simulator will consume a lot of space and difficult to reuse for other project. In addition, design verification for control room and I&C system need to start at the early stage of a project and is usually an iterative process with the design work. Build a control room facility for simulator needs a lot of time and is difficult to modify once constructed. To make the simulator more flexible and match the project schedule, virtual reality technology can be used to replace or extend traditional control room simulator with approximately the same arrangement, environment, human machine interface and function. In the full scope engineering simulator of HPR1000 unit, virtual reality control room interface has been designed as an extension of real control room implementation. The designer or operator can control and monitor the power plant in virtual reality environment, which just feels like real control room. It also can be used for other type of reactor by connecting to other simulator server and adding corresponding control room model in virtual reality software. With this preliminary application, control room simulator can be implemented in a short time and flexible for modification, which give designer more time and space for design verification and optimization. Once it applied in training simulator of nuclear power plant in future, it may provide a low cost and flexible option for operator training.

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