Design of an Ethernet Bus Interface Controller in a Nuclear Power Plant Simulator

2010 ◽  
Author(s):  
Lixuan Lu ◽  
Dong Le
Keyword(s):  
Control System ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Communication Networks ◽  
Nuclear Power ◽  
Power Plants ◽  
Distributed Control System ◽  
Training Requirements ◽  
The Many ◽  
And Training

Obsolescence presents great challenge to Nuclear Power Plants (NPP) and plant simulators around the world. Old designs will have to be either modified, or replaced by new designs, in order to simplify maintenance, increase availability and meet ever-increasing operational and training requirements. Control system upgrade and Distributed Control System (DCS) design for both old plants and new builds have become the center of interest. In a DCS, communication networks connect control systems together to allow the exchange of information and feedback. Among the many communication network protocols, Ethernet can be a promising one. This paper describes a new Ethernet Bus Interface Controller (eBIC) used in the Input/Output (I/O) system of a Nuclear Power Plant (NPP) simulator in Canada.

Study on Reliability Analysis of Distributed Control System of Nuclear Power Plant

2011 ◽  
Vol 383-390 ◽  
pp. 4281-4285
Author(s):  
Hu Wang ◽  
Shao Hua Li ◽  
Guang Cai Qi ◽  
Fu Sheng Lai
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Distributed Control ◽  
Preliminary Analysis ◽  
Nuclear Power ◽  
Power Plants ◽  
Continuous Operation ◽  
Distributed Control System ◽  
Control Methods ◽  
Reliability Parameters

The reliability of the nuclear power plant DCS is analyzed using Markov process to establish a mathematical model. And the initial use of the model on the three indicators of reliability parameters of nuclear power plants is calculated. The results showed that the model is correct,reliable and error rate is 9×10-10.DCS applies to preliminary analysis of the reliability of nuclear power DCS. Nuclear power plant DCS reliability is high enough, the minimum time of continuous operation is up to 66667 h, compared to conventional control methods more safe and reliable.

Analysis of Cyber Security Incident in South Korean Nuclear Power Plant and Cyber Security Solutions for Nuclear Power Industrial Control System

2017 ◽  
Author(s):  
Yufang Bian ◽  
Jing Li ◽  
Baojuan Yin
Keyword(s):  
Control System ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Cyber Security ◽  
Nuclear Power ◽  
Power Plants ◽  
Industrial Control System ◽  
Industrial Control ◽  
Security Incident ◽  
South Korean

South Korean nuclear power plant information leakage incident occurred in 2014. A hacker on the Internet issued four compressed files of Korean nuclear power plant, and threatened the nuclear power plant to stop related units. This paper reviews the cyber security incident and analyses the cause of the event. Then, it analyzes the security risks of industrial control system in nuclear power plants and proposes some suggestions to strengthen nuclear power cyber security.

Research on Probabilistic Safety Assessment (PSA) Method of Safety Class Distributed Control System (DCS) in Nuclear Power Plant Based on Fuzzy Markov Process

2020 ◽  
Author(s):  
Tian Xufeng ◽  
Yan Hao
Keyword(s):  
Control System ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Markov Process ◽  
Distributed Control ◽  
Nuclear Power ◽  
Safety Assessment ◽  
Fault Tree ◽  
Simulation Method ◽  
Distributed Control System

Abstract Safety class DCS (Distributed Control System) in nuclear power plant is characterized by multi-state interaction, complex function and unknown fault mechanism, which limits the use of tradition PSA (Probabilistic Safety Assessment) method such as event tree and fault tree. An improved dynamic probabilistic security simulation method is proposed based on fuzzy Markov process to quantitative evaluation the risk of Safety class DCS in nuclear power plant, which resolved the failure uncertainty problem without in-depth understanding of failure mechanism. Firstly, the fuzzy fault tree reliability evaluation model is established based on fuzzy theory and FTA (Fault Tree Analysis), which describes the probability and degree of failure with fuzzy number. Then, the fuzzy fault tree is transformed into fuzzy Markov chain, this model is described mathematically, and the reliability indexes are simulated and analyzed with Monte Carlo simulation method, the change of system safety performance in long-term operation is obtained. Finally, the scientificity and effectiveness is verified by the example of redundant analog output module of safety class DCS in nuclear plant.

Teaching of Nuclear Power Plant Safety at the National Technical University of Ukraine Within the New Course in Safety Culture

2012 ◽  
Author(s):  
Vasilij V. Begun ◽  
Sergij V. Begun ◽  
Olena O. Kilina
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Safety Culture ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Safety Analysis ◽  
Nuclear Industry ◽  
Educational Course ◽  
And Training

The necessity of safety analysis methods and probable scenarios of accidents teaching in the education of experts for nuclear industry in Ukraine has been realised only after the Chernobyl accident. We developed the content of the first educational course in probabilistic safety analysis in 1995 based on the experience of the countries having developed nuclear power, the USA first of all, and on the training course of the Idaho National Laboratory. After this in 1996 the new course in probabilistic safety analysis of nuclear power plant (NPP) was adopted at our university. The new educational course in safety for students was developed and adopted in 2009 educational year - “Safety culture at nuclear installations of Ukraine”. Education and training in safety culture in higher educational institutions and in the nuclear power plants is a part of the general modern process of maintenance of safety, it is recommended by IAEA standards. The principles of safety culture are taken as a basis of the modern concept of safety of nuclear power plants. This work has received a positive appreciation from the management of departments of safety and training of the personnel of operating organization National Nuclear Energy Generating Company Energoatom (NNEGC Energoatom) and from other leaders of nuclear industry. The content of this educational course was discussed at the international scientific conferences on safety culture in 2008 and 2010, and was preliminary printed in the professional journal «Nuclear and radiation safety». The purposes of education have been defined as a survey, generalizing course on safety of the NPP with an allocation of safety issues on the foreground. Practical questions of the equipment and NPP systems work, their interaction in emergencies and the role of the human-operator are studied. The procedure of failure analysis at NPP is studied. Students analyze equipment work, root and direct causes of incidents. Methods of estimation of safety conditions based on observable operational indicators are studied. Parameters, variables and indicators of safety culture are studied. As a result of gained experience we have come to the conclusion about high advisability of educational courses in safety for students. Specially formed knowledge and education in the field of safety from a student’s bench are the basis of safety culture of the future nuclear industry expert.

A Nuclear Power Plant Distributed Control System

1997 ◽  
Vol 30 (18) ◽  
pp. 391-396
Author(s):  
Mathilde Aimar ◽  
Gilles Arnaud ◽  
Michel Dumas
Keyword(s):  
Control System ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Distributed Control ◽  
Nuclear Power ◽  
Distributed Control System

Sensitivity Analysis for Human Errors of a Chemical and Volume Control System at Nuclear Power Plant by Soft Control

2017 ◽  
Author(s):  
Zhang Yuxin ◽  
Yang Kunze
Keyword(s):  
Control System ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Power Plants ◽  
Failure Modes ◽  
Sensitivity Analyses ◽  
Volume Control ◽  
Pressurized Water ◽  
Human Errors

The introduction of soft controls into the main control room may provide a more convenient environment for operations, but also may introduce new types of human errors and new risks into the nuclear power plants. In this paper, taking the Chemical and Volume Control System (CVCS) at pressurized water reactor nuclear power plant as an example, the task analysis of operating procedures for starting the CVCS under a normal shut-down operation condition, the potential failure modes during operators executing each step of operating procedures and the dependency analysis of sub-tasks are presented. Furthermore, the sensitivity analyses are conducted for identifying probability importance and critical importance of each model parameter. The countermeasures for preventing and reducing the human errors of soft controls are discussed.

Fuzzy multi-objective decision making approach for nuclear power plant installation

2020 ◽  
Vol 39 (5) ◽  
pp. 6339-6350
Author(s):  
Esra Çakır ◽  
Ziya Ulukan
Keyword(s):  
Linear Programming ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Energy Supply ◽  
Energy Demand ◽  
Nuclear Power ◽  
Power Plants ◽  
Total Duration ◽  
Objective Functions ◽  
Multi Objective

Due to the increase in energy demand, many countries suffer from energy poverty because of insufficient and expensive energy supply. Plans to use alternative power like nuclear power for electricity generation are being revived among developing countries. Decisions for installation of power plants need to be based on careful assessment of future energy supply and demand, economic and financial implications and requirements for technology transfer. Since the problem involves many vague parameters, a fuzzy model should be an appropriate approach for dealing with this problem. This study develops a Fuzzy Multi-Objective Linear Programming (FMOLP) model for solving the nuclear power plant installation problem in fuzzy environment. FMOLP approach is recommended for cases where the objective functions are imprecise and can only be stated within a certain threshold level. The proposed model attempts to minimize total duration time, total cost and maximize the total crash time of the installation project. By using FMOLP, the weighted additive technique can also be applied in order to transform the model into Fuzzy Multiple Weighted-Objective Linear Programming (FMWOLP) to control the objective values such that all decision makers target on each criterion can be met. The optimum solution with the achievement level for both of the models (FMOLP and FMWOLP) are compared with each other. FMWOLP results in better performance as the overall degree of satisfaction depends on the weight given to the objective functions. A numerical example demonstrates the feasibility of applying the proposed models to nuclear power plant installation problem.

Human reliability in non-destructive inspections of nuclear power plant components: modeling and analysis

2019 ◽  
Vol 7 (2B) ◽  
Author(s):  
Vanderley Vasconcelos ◽  
Wellington Antonio Soares ◽  
Raissa Oliveira Marques ◽  
Silvério Ferreira Silva Jr ◽  
Amanda Laureano Raso
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Human Factors ◽  
Nuclear Power ◽  
Power Plants ◽  
Failure Modes ◽  
Cooling System ◽  
Human Reliability ◽  
Non Destructive ◽  
Plant Components

Non-destructive inspection (NDI) is one of the key elements in ensuring quality of engineering systems and their safe use. This inspection is a very complex task, during which the inspectors have to rely on their sensory, perceptual, cognitive, and motor skills. It requires high vigilance once it is often carried out on large components, over a long period of time, and in hostile environments and restriction of workplace. A successful NDI requires careful planning, choice of appropriate NDI methods and inspection procedures, as well as qualified and trained inspection personnel. A failure of NDI to detect critical defects in safety-related components of nuclear power plants, for instance, may lead to catastrophic consequences for workers, public and environment. Therefore, ensuring that NDI is reliable and capable of detecting all critical defects is of utmost importance. Despite increased use of automation in NDI, human inspectors, and thus human factors, still play an important role in NDI reliability. Human reliability is the probability of humans conducting specific tasks with satisfactory performance. Many techniques are suitable for modeling and analyzing human reliability in NDI of nuclear power plant components, such as FMEA (Failure Modes and Effects Analysis) and THERP (Technique for Human Error Rate Prediction). An example by using qualitative and quantitative assessesments with these two techniques to improve typical NDI of pipe segments of a core cooling system of a nuclear power plant, through acting on human factors issues, is presented.

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