Operational Results of Radionuclide Assay System at the Kori Nuclear Power Plant: Status and Results

2001 ◽  
Author(s):  
Jin Beak Park ◽  
Kun Jai Lee ◽  
Duck Won Kang ◽  
Dae Hwan Kim
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Assay System ◽  
Prediction Program ◽  
And Control ◽  
Non Destructive ◽  
Waste Drums ◽  
Gamma Scanning ◽  
Control Facility

Abstract In 1996, the fully automated radionuclide assay system, which is used for the non-destructive analysis and for the evaluation of radioactive waste drums, was installed at Kori nuclear power plant site and started to operate. The system is composed of gamma scanning hardware facility, equipment for separation and detection of non-gamma radionuclide, scaling factor prediction program, and control facility for radionuclide assay system. In this study, the operational status and results of radionuclide assay system are investigated from the experience of several years of operation. The results of the radionuclide assay system are compared with the results of dose to curie conversion program (DOSE).

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.

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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