Research on Nuclear Turbine Control and Protection System Based on DCS Integrated Technical Solution

2021 ◽  
Author(s):  
Guilian Shi ◽  
Jikun Wang ◽  
Jingbin Gao
Keyword(s):  
Control System ◽  
Power Plant ◽  
Nuclear Power ◽  
Power Plants ◽  
Protection System ◽  
Feasibility Analysis ◽  
Technical Solution ◽  
Good Prospect ◽  
Test Results ◽  
Distribute Control System

Abstract Turbine Control System (DEH) and Turbine Protection System (ETS) are important auxiliary systems for turbines. Normally DEH and ETS are supplied by turbine manufacturers. This paper investigates the operation experience in Nuclear Power Plants (NPPs) in China, there are many problems including information security, maintenance inconvenience, long supply cycle guarantee, high cost and so on in DEH and ETS. This paper analyzes the problems and tries to get the reasons why DEH&ETS have these problems. The Distribute Control System (DCS) technology has been widely used in nuclear power plant in now days, so this paper puts forward a technical solution based on the safety DCS and non-safety DCS platform to realize the DEH and ETS, and according to the feasibility analysis of products, and the test results based on engineering prototype, the solution can solve the problems of DEH and ETS effectively, some performances of the DEH&ETS have been improved, and the solution has a good prospect in further.

Ammonia Bottoming Cycle Development at Electricité de France for Nuclear Power Plants

1981 ◽  
Author(s):  
J. Fleury
Keyword(s):  
Power Plant ◽  
Heat Exchangers ◽  
Nuclear Power ◽  
Power Plants ◽  
Economic Conditions ◽  
Air Cooling ◽  
Test Results ◽  
Power Station ◽  
Major Benefit ◽  
Dry Cooling

An ammonia bottoming cycle is under active development at Electricité de France. To be implemented in a nuclear power plant downstream from the steam cycle, shortened for this application, its purpose is to make it possible to practice air cooling in satisfactory economic conditions. After an analysis of the main parameters of the bottoming cycle (H2O/NH3) (i.e., back pressure and temperature differences in the heat exchangers) its advantages are enumerated: in addition to those the dry cooling concept, the major benefit consists of the fact that the bottoming cycle makes use of low atmospheric temperatures in winter, producing a significant increase in the power output, just when it is most needed in many geographic locations. Emphasis is placed on the experimental work performed on E.D.F. test facilities and the construction of a 20-MWe demonstration bottoming cycle power plant at Gennevilliers power station. A brief account is given of test results and experimental programs.

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.

scholarly journals Early quantification of reliability for a safety critical and control system: a case study of reactor core cooling system

2018 ◽  
Vol 7 (2.12) ◽  
pp. 248
Author(s):  
Vinay Kumar ◽  
Suraj Gupta ◽  
Anil Kumar Tripathi
Keyword(s):  
Control System ◽  
Power Plant ◽  
Nuclear Power ◽  
Power Plants ◽  
Cooling System ◽  
Reactor Core ◽  
Safety Critical ◽  
Core Cooling ◽  
And Control

Using Probabilistic Reliability analysis for Quantifying reliability of a system is already a common practice in Reliability Engineering community. This method plays an important role in analyzing reliability of nuclear plants and its various components. In Nuclear Power Plants Reactor Core Cooling System is a component of prime importance as its breakdown can disrupt Cooling System of power plant. In this paper, we present a framework for early quantification of Reliability and illustrated with a Safety Critical and Control System as case study which runs in a Nuclear Power Plant.  

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.

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.

Research on the Computerized Symptom-Oriented Procedures of Nuclear Power Plants

2008 ◽  
Author(s):  
Fei Liu ◽  
Zhijian Zhang ◽  
Minjun Peng
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Interface Design ◽  
Nuclear Power ◽  
Power Plants ◽  
Test Results ◽  
Pressurized Water ◽  
Water Reactors ◽  
Steam Generator Tubes ◽  
Emergency Operating

New methods of information presentation and interface design are changing the working conditions in the modern Nuclear Power Plant (NPP) control room. Symptom-oriented EOPs (SOPs) with their structures and practical application are described. The Computerized Symptom-oriented Operating Procedures (CSOP) is researched, which can help the operator analyze all the symptom signals of steam generator tubes rupture (SGTR) and provide the computerized procedures corresponding to the symptom signals. This paper analyzes the accident of SGTR; the accident management of SGTR is important in reactor safety because SGTR is one of the relatively high-frequency events in pressurized water reactors PWRs. The symptom signals of SGTR and the possible accidents corresponding to the symptom signals are analyzed. The homologous measures of symptoms are summarized. The disposal of SGTR adopts the method of based on symptoms. The programs are developed by VxWorks that is a real-time operating system. The debugging of programs is processed on simulator. The test results indicated that the programs can provide operating procedures according to the symptoms of accidents. After adopting the Computerized Emergency Operating Procedures, the labor intensity and mental burden of operators are lightened. Computerized Emergency Operating Procedures can enhance the reliability, safety and efficiency of Nuclear Power Plant.

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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