Integrated Software Safety Analysis Method for Digital I&C Systems

2008 ◽  
Author(s):  
Hui-Wen Huang ◽  
Hung-Chih Hung ◽  
Chunkuan Shih ◽  
Swu Yih ◽  
Ming-Huei Chen ◽  
...  
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Simulation Analysis ◽  
Analysis Method ◽  
Software Failure ◽  
Integrated Methodology ◽  
Software Fault ◽  
And Control ◽  
Tree Method

The digitalized Instrumentation and Control (I&C) system of Nuclear power plants can provide more powerful overall operation capability, and user friendly man-machine interface. The operator can obtain more information through digital I&C system. However, while I&C system being digitalized, three issues are encountered: 1) software common-cause failure, 2) the interaction failure between operator and digital instrumentation and control system interface, and 3) the non-detectability of software failure. These failures might defeat defense echelons, and make the Diversity and Defense-in-Depth (D3) analysis be more difficult. This work developed an integrated methodology to evaluate nuclear power plant safety effect by interactions between operator and digital I&C system, and then propose improvement recommendations. This integrated methodology includes component-level software fault tree, system-level sequence-tree method and nuclear power plant computer simulation analysis. Software fault tree can clarify the software failure structure in digital I&C systems. Sequence-tree method can identify the interaction process and relationship among operator and I&C systems in each D3 echelon in a design basis event. Nuclear power plant computer simulation analysis method can further analyze the available backup facilities and allowable manual action duration for the operator when the digital I&C fail to function. Applying this methodology to evaluate the performance of digital nuclear power plant D3 design, could promote the nuclear power plant operation safety. The operator can then trust the nuclear power plant than before, when operating the highly automatic digital I&C facilities.

Technical Architecture About Safety I&C System Software V&V in Nuclear Power Plant

2017 ◽  
Author(s):  
Shengchao Wang ◽  
Pengfei Gu ◽  
Wangping Ye ◽  
Weihua Chen
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Nuclear Safety ◽  
Software Failure ◽  
Digital Instrumentation ◽  
Technical Architecture ◽  
Technical Model ◽  
Specific Implementation ◽  
And Control

Digital instrumentation and control (I&C) system has been widely applied in nuclear power plant (NPP), which brings some new problems like software failure. The software failure is easy to come into being the common cause failure (CCF), leading to the failure of the whole protection system for NPP, thus endangering the safety of the NPP. In order to obtain the high quality software for computer important to safety, it is necessary to implement the software verification and validation (V&V) to guarantee that the software can completely and correctly meet the expected requirements of safety functions and performances. Moreover, for the guidance of software V&V and to strengthen the reliability of the software, laws and regulation standards related to the software V&V, were analyzed. On the basis of requirements of the laws and regulations standards and the results of analysis, a technical architecture about nuclear safety digital instrumentation and control system (DCS) software V&V was proposed, which consists of a technical model of software V&V and a general quality assurance (QA) system. The technical model of software V&V mainly illustrated some problems and discussed how to deal with it on the specific implementation of V&V activities and tasks. Meanwhile, in order to support the software V&V activities and tasks carried out efficiently, the general QA system, corresponding to the technical model of software V&V, was established which can supply the visual evidence for quality control process. At this point, it is expected that the results as studied above can provide some technical references in the transformation, formulating or modifying related standards of China and to promote the quality of nuclear safety DCS software.

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.

Modernization of the Safety I&C at the Dukovany VVER 440/213 Nuclear Power Plant

2009 ◽  
Author(s):  
Jean-Michel Palaric ◽  
Philippe Rebreyend ◽  
Philippe Mouly ◽  
Claude Esmenjaud ◽  
Frantisˇek Dalik
Keyword(s):  
Industrial Organization ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Digital Technologies ◽  
Design Criteria ◽  
Special Focus ◽  
Main Design ◽  
And Control

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.

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
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