NE-OBT and TFWT activity concentrations in wild plants in the vicinity of the PHWR nuclear power plant and control regions of the tropical monsoonal climatic region of the Indian subcontinent

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.

Download Full-text

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

Volume 5: Fuel Cycle and High and Low Level Waste Management and Decommissioning; Computational Fluid Dynamics (CFD), Neutronics Methods and Coupled Codes; Instrumentation and Control ◽

10.1115/icone17-75706 ◽

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.

Download Full-text

Modeling uncertainty of instrument and control system of nuclear power plant

Annals of Nuclear Energy ◽

10.1016/j.anucene.2019.107207 ◽

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

Download Full-text

Networked control approaches for a nuclear power plant pressurizer subsystem* *This work is supported by the Control Engineering Research Group of HAS at Budapest University of Technology and Economics. The support of the Hungarian National Office for Research and Technology through grants TECH 08-A2/2-2008-0088 is gratefully acknowledged. This research work has been partially supported by the Hungarian Scientific Research Fund through grant no. K67625. G.S. is a grantee of the Bolyai János Research Scholarship of the Hungarian Academy of Sciences. The authors gratefully acknowledge the continuous support of the members of the INC Refurbishment Project at the Paks Nuclear Power Plant. The authors also thank István Varga at the Systems and Control Laboratory for his project management work.

IFAC Proceedings Volumes ◽

10.3182/20090924-3-it-4005.00054 ◽

2009 ◽

Vol 42 (20) ◽

pp. 316-321

Author(s):

G. Szederkényi ◽

T. Péni ◽

P. Gáspár ◽

J. Bokor

Keyword(s):

Power Plant ◽

Nuclear Power Plant ◽

Nuclear Power ◽

Research Work ◽

Hungarian Academy ◽

Engineering Research ◽

National Office ◽

University Of Technology ◽

Research Scholarship ◽

And Control

Download Full-text

The Use of System Codes in Scaling Studies: Relevant Techniques for Qualifying NPP Nodalizations for Particular Scenarios

Science and Technology of Nuclear Installations ◽

10.1155/2014/138745 ◽

2014 ◽

Vol 2014 ◽

pp. 1-13 ◽

Cited By ~ 3

Author(s):

V. Martinez-Quiroga ◽

F. Reventos

Keyword(s):

Experimental Data ◽

Power Plant ◽

Nuclear Power Plant ◽

Nuclear Power ◽

Safety Analysis ◽

Small Scale ◽

Plant Operation ◽

Essential Step ◽

Hydraulic Safety ◽

And Control

System codes along with necessary nodalizations are valuable tools for thermal hydraulic safety analysis. Qualifying both codes and nodalizations is an essential step prior to their use in any significant study involving code calculations. Since most existing experimental data come from tests performed on the small scale, any qualification process must therefore address scale considerations. This paper describes the methodology developed at the Technical University of Catalonia in order to contribute to the qualification of Nuclear Power Plant nodalizations by means of scale disquisitions. The techniques that are presented include the so-calledKv-scaled calculation approach as well as the use of “hybrid nodalizations” and “scaled-up nodalizations.” These methods have revealed themselves to be very helpful in producing the required qualification and in promoting further improvements in nodalization. The paper explains both the concepts and the general guidelines of the method, while an accompanying paper will complete the presentation of the methodology as well as showing the results of the analysis of scaling discrepancies that appeared during the posttest simulations of PKL-LSTF counterpart tests performed on the PKL-III and ROSA-2 OECD/NEA Projects. Both articles together produce the complete description of the methodology that has been developed in the framework of the use of NPP nodalizations in the support to plant operation and control.

Download Full-text