Design and Realization of Control System for New Nuclear Fuel Elevator System

2014 ◽  
Vol 631-632 ◽  
pp. 664-668
Author(s):  
Yu Fang
Keyword(s):  
Control System ◽  
Software Architecture ◽  
Nuclear Fuel ◽  
Pid Control ◽  
Nuclear Power ◽  
Power Station ◽  
Nuclear Assembly ◽  
Safety And Reliability ◽  
User Friendly ◽  
High Radioactivity

As one of the key equipment for handling nuclear assembly in nuclear power station, the Nuclear Fuel Elevator (NFE) is mainly used to handle the new assembly and examine the spent assembly. Considering the safety and reliability for the high radioactivity environment, the control system with two levels of hardware controllers and module hierarchical software architecture is proposed. The HMI which is convenient and user-friendly is also developed for operator. The load protection and dynamic PID-control is mentioned in detail.

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.

scholarly journals Tritium in Snow Cover of the Areas Affected by Nuclear Fuel Enterprises in the Urals

2014 ◽  
pp. 102-113
Author(s):  
Keyword(s):  
Snow Cover ◽  
Nuclear Power Station ◽  
Nuclear Fuel ◽  
Nuclear Power ◽  
Control Area ◽  
Power Station ◽  
The Urals ◽  
Background Values ◽  
Area North ◽  
Source Of Pollution

The results of many-year studies of tritium concentrations in the snow cover in various areas of the Urals are reported. The investigated region included impact areas of the “Mayak” enterprise (South Ural), Beloyarka nuclear power station (Middle Ural), the booster separating part fall/control area (North Ural). Maps-schemes show areas at various distances from the source of pollution where tritium levels exceed the background values.

scholarly journals On a Long Term Strategy for the Success of Nuclear Power

2017 ◽  
Author(s):  
Bruno Merk ◽  
Dzianis Litskevich ◽  
Karl R. Whittle ◽  
Mark Bankhead ◽  
Richard Taylor ◽  
...  
Keyword(s):  
Nuclear Fuel ◽  
Nuclear Power ◽  
Nuclear Reactor ◽  
Spent Nuclear Fuel ◽  
Nuclear Reactors ◽  
Theoretical Perspective ◽  
Strategic Development ◽  
Safety And Reliability ◽  
Water Reactors

The current generation of nuclear reactors are evolutionary in design, mostly based on the technology originally designed to power submarines, and dominated by Light Water Reactors. The aims of the GenIV consortium are driven by sustainability, safety and reliability, economics, and proliferation resistance. The aims are extended here to encompass the ultimate and universal vision for strategic development of energy production, the ‘perpetuum mobile’ – at least as close as possible. We propose to rethink nuclear reactor design with the mission to develop a system which uses no fresh resources and produces no fresh waste during operation as well as generates power safe and reliably in economic way. The results of the innovative simulations presented here demonstrate that, from a theoretical perspective, it is feasible to fulfil the mission through the reuse of spent nuclear fuel from currently operating reactors as the fuel for a new reactor. The produced waste is less burdensome than current spent nuclear fuel which is used as feed to the system. However, safety, reliability and operational economics will need to be demonstrated to create the basis for the long term success of nuclear reactors as a major carbon free, sustainable, and applied highly reliable energy source.

Research and Application of Safety Information and Control System of Nuclear Power Station

2010 ◽  
Author(s):  
Liming Zhang ◽  
Weijun Huang ◽  
Yongbin Sun ◽  
Guojin Jiang
Keyword(s):  
Control System ◽  
Nuclear Power Station ◽  
Nuclear Power ◽  
Design Principle ◽  
Safety Information ◽  
Engineering Application ◽  
Power Station ◽  
Safe State ◽  
And Control

The thesis researches the Safety Information and Control System (SICS) design principle and introduce engineering application in CPR1000 nuclear power station in China. The SICS provides sufficient control and monitoring means to bring and maintain the plant in a safe state as a backup of Main computerized Control Mean (MCM), in any plant conditions that are probable during a planed or unplanned unavailability of the MCM. The successful engineering application of SICS in different digital I&C system platform are introduced in the paper. The thesis gives the research conclusion for new general SICS of digital I&C system.

scholarly journals Tritium Migration from Nuclear Fuel Enterprises to Drinking Water Sources in the Urals

2013 ◽  
pp. 90-100
Author(s):  
Keyword(s):  
Drinking Water ◽  
Nuclear Power Station ◽  
Nuclear Fuel ◽  
Water Contamination ◽  
Nuclear Power ◽  
Pollution Source ◽  
Power Station ◽  
The Urals ◽  
Tritium Content ◽  
Water Wells

The paper reports on results of the investigation of tritium content in the sources of drinking water (wells, bore holes, in the areas affected by Beloyarskaya nuclear power station and the “Mayak” enterprise (the Urals). The plans and maps of the wells and bore-holes water contamination in the said areas are presented. Correlation of the tritum concentration in drinking water with the distance to the pollution source and the depth of water location has been demonstrated.

Automated control of nuclear fuel use in a nuclear power station containing the RBMK reactor

1986 ◽  
Vol 61 (3) ◽  
pp. 768-770
Author(s):  
A. P. Eperin ◽  
M. P. Umanets ◽  
B. M. Svecharevskii ◽  
S. A. Andreev
Keyword(s):  
Nuclear Power Station ◽  
Nuclear Fuel ◽  
Nuclear Power ◽  
Rbmk Reactor ◽  
Power Station ◽  
Fuel Use ◽  
Automated Control
Sign in / Sign up

Export Citation Format

Share Document