VVER 1000 Pressurizer System and Control Modelling in Dymola

2018 ◽  
Author(s):  
Anna Fořtová ◽  
Filip Ježek
Keyword(s):  
Automatic Control ◽  
Nuclear Power ◽  
Reactor Power ◽  
Self Control ◽  
Primary Circuit ◽  
Saturation State ◽  
Power Change ◽  
And Control ◽  
Control Regime ◽  
Made In

The pressurizer is responsible for controlling the pressure and temperature in the primary circuit of the nuclear power plant. It is basically a pressure vessel, filled partially with water and partially with steam at saturation state. The controlling process can be described by two regimes, either by the self-control regime or by the automatic control regime. This paper is describing the simplified automatic control regime on the model of the pressurizer in the primary circuit of VVER 1000 made in Dymola software with the ClaRa library. Reactor power change and corresponding steam generator power change are the actuators in the simulation. The behaviour of the coolant level and pressure in the pressurizer is simulated in the model and it is then compared with data provided by the supplier of VVER 1000.

Protocol Analysis and Action Classification in the Evaluation of an Advanced Annunciator System Design

1989 ◽  
Vol 33 (16) ◽  
pp. 1064-1067
Author(s):  
Thomas F. Sanquist ◽  
Yushi Fujita
Keyword(s):  
Nuclear Power ◽  
Protocol Analysis ◽  
Verbal Protocols ◽  
Action Classification ◽  
Behavioral Classification ◽  
Machine Interface ◽  
Discrete Values ◽  
Effective Diagnosis ◽  
And Control ◽  
Made In

The use of protocol analysis and behavioral classification for evaluating advanced display concepts is described. Three experienced nuclear power plant operators solved problems in a full-scale simulator which employed an alarm suppression logic in the annunciator display. Verbal protocols and behavioral actions were collected as operators solved the problems, and were compared with protocols in which the alarm suppression logic was not used. The results indicated that more observations of discrete values and more control actions were made in the condition employing the alarm suppression scheme, suggesting more effective diagnosis and control with this type of man-machine interface.

I&C Integrated Test Phase of the Mochovce Nuclear Power Plant, Units 3 and 4

2014 ◽  
Author(s):  
Antonio Ciriello ◽  
Stefan Kümmerling
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Slovak Republic ◽  
Reactor Power ◽  
Test Phase ◽  
Acceptance Test ◽  
Safety Systems ◽  
And Control ◽  
Reactor Protection System

This paper briefly introduces the safety instrumentation and control (I&C) system (Teleperm® XS) designed for the nuclear power plant in Mochovce units 3 and 4 (Slovak Republic). The overall I&C architecture of the concerned nuclear power plant is shortly introduced as well. An overview is given on the different test phases for the hardware and software I&C modules. The integrated I&C test concept and its implementation is presented as well as the description of the integrated test phase in the test bay in Erlangen (Germany). After a successful completion of the integrated test phase for unit 3, the Factory Acceptance Test (FAT) and the erection phase have been started for the concerned I&C safety systems (e.g., the Reactor Protection System and the Reactor Power Limitation System). This paper will also present the significant advantages and specifics of performing the concerned I&C tests in the aforementioned test bay.

scholarly journals Transient Study on the HTR-PM with TINTE-vPower Coupling Code Package

2020 ◽  
Vol 2020 ◽  
pp. 1-14
Author(s):  
Jun Sun ◽  
Ximing Sun ◽  
Yanhua Zheng
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Water Flow ◽  
Nuclear Power ◽  
Data Exchange ◽  
Reactor Power ◽  
Normal Operation ◽  
Primary Circuit ◽  
Fuel Temperature ◽  
Operation Conditions

The high-temperature gas-cooled reactor pebble-bed module (HTR-PM) nuclear power plant consists of two nuclear steam supply system modules, each of which drives the steam turbine by the superheated steam flow and is fed by the heated-up water flow. The shared steam/water system induces mutual effects on normal operation conditions and transients of the nuclear power plant, which is worthy of safety concerns and intensive study. In this paper, a coupling code package was developed with the TINTE and vPower codes to understand how the HTR-PM operated. The TINTE code was used to analyze the reactor core and primary circuit, while the vPower code simulated the steam/water flow in the conventional island. Two TINTE models were built and coupled to one vPower model through the data exchange in the steam generator models. Using this code package, two typical transients were simulated by decreasing the primary flow rate or introducing the negative reactivity of one module. Important parameters, including the reactor power, the fuel temperature, and the reactor inlet and outlet helium temperatures of two modules, had been studied. The calculation results preliminarily proved that this code package can be further used to evaluate working performance of the HTR-PM.

An Efficient Approach for Modeling and Control of a Quadrotor

2016 ◽  
Vol 4 (2) ◽  
pp. 1-16
Author(s):  
Ahmed S. Khusheef
Keyword(s):  
Pid Control ◽  
Control Method ◽  
Mechanical Design ◽  
Loop Control ◽  
Modeling And Control ◽  
Loop Control System ◽  
And Control ◽  
Close Loop Control ◽  
Close Loop Control System ◽  
Made In

 A quadrotor is a four-rotor aircraft capable of vertical take-off and landing, hovering, forward flight, and having great maneuverability. Its platform can be made in a small size make it convenient for indoor applications as well as for outdoor uses. In model there are four input forces that are essentially the thrust provided by each propeller attached to each motor with a fixed angle. The quadrotor is basically considered an unstable system because of the aerodynamic effects; consequently, a close-loop control system is required to achieve stability and autonomy. Such system must enable the quadrotor to reach the desired attitude as fast as possible without any steady state error. In this paper, an optimal controller is designed based on a Proportional Integral Derivative (PID) control method to obtain stability in flying the quadrotor. The dynamic model of this vehicle will be also explained by using Euler-Newton method. The mechanical design was performed along with the design of the controlling algorithm. Matlab Simulink was used to test and analyze the performance of the proposed control strategy. The experimental results on the quadrotor demonstrated the effectiveness of the methodology used.

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