Study of the Characteristic Response of Pressure Control System in Order to Obtain the Design Parameters of the New Control System MARK VI Turbine in Cofrentes Nuclear Power Plant

2010 ◽  
Author(s):  
Laura Bucho´ ◽  
Mari´a Jose´ Palomo ◽  
Juan Ignacio Vaquer ◽  
Bele´n Lo´pez ◽  
Gregorio Rui´z ◽  
...  
Keyword(s):  
Control System ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Technical Specification ◽  
Pressure Control ◽  
Design Parameters ◽  
Sensor Signal ◽  
Bode Plot ◽  
Pressure Control System

This paper presents the results obtained from the IBE-CNC/DAQ-090827 project, conducted by the company “Titania Servicios Tecnolo´gicos, S.L.” in collaboration with the “Instituto de Seguridad Industrial, Radiofi´sica y Medioambiental” (ISIRYM), in the “Universidad Polite´cnica de Valencia”, for the company “Iberdrola Generacio´n S.A”. The objective is the acquisition of the pressure sensor signal and the measurement at points C85 and N32 from the cabin of the Turbine Control System in Cofrentes Nuclear Power Plant. With the study of previous data, one can obtain the Bode plot of the crossed signals as requested in the technical specification IM 0191 I. Frequency response (i.e. how the system varies its gain and offset depending on the frequency) defines the dynamics.

scholarly journals Parametric analysis of pressure control system for Lungmen nuclear power plant

2012 ◽  
Vol 14 ◽  
pp. 1082-1086
Author(s):  
Chiung-Wen Tsai ◽  
Chunkuan Shih ◽  
Jong-Rong Wang ◽  
Hao-Tzu Lin ◽  
Su-Chin Cheng ◽  
...  
Keyword(s):  
Control System ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Parametric Analysis ◽  
Nuclear Power ◽  
Pressure Control ◽  
Pressure Control System

Research on Pressurizer Pressure Control System of 900MW Pressurized Water Reactor Nuclear Power Plant

2013 ◽  
Vol 718-720 ◽  
pp. 1215-1220
Author(s):  
Guo Duo Zhang ◽  
Xu Hong Yang ◽  
Si Yu Qiao ◽  
Yu Jun Wu
Keyword(s):  
Control System ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Control Method ◽  
Pressure Control ◽  
Sharp Change ◽  
Control Technology ◽  
Pressurized Water ◽  
Pressure Control System

It is of vital importance for the pressurizer to maintain the pressure of primary coolant because the sharp change of coolant pressure has a direct impact on the security of reactor. The study of pressurizers pressure control method is highly important and meaningful. This paper presents the researching and designing on pressure control system of a pressurizer implemented in a nuclear power plant. Both the present situation of the nuclear power and some relevant background have been briefly introduced. Proceeding on the records of simulation, we succeed in establishing the applied modeling of pressurizer and further propose the PID control technology working as control algorithm. The best set of controller parameters are chosen through comparing the results including regulation time, overshoot suppression and stability. On the base of such control method, we attempt to add neural network control technology to achieve further improvement, which turns out available and satisfying.

scholarly journals On study of steam bypass and pressure control system for Lungmen nuclear power plant

2011 ◽  
Vol 15 ◽  
pp. 5328-5332 ◽  
Author(s):  
Chiung-Wen Tsai ◽  
Chunkuan Shih ◽  
Jong-Rong Wang ◽  
Hao-Tzu Lin ◽  
Su-Chin Cheng ◽  
...  
Keyword(s):  
Control System ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Pressure Control ◽  
Pressure Control System

Recirculation Pump Speed Control System Upgrades in Nuclear Boiling Water Reactors

2008 ◽  
Author(s):  
James W. Morgan
Keyword(s):  
Control System ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Flow Control ◽  
Nuclear Power ◽  
Boiling Water ◽  
Boiling Water Reactors ◽  
Pump Speed ◽  
Water Reactors ◽  
Generator Sets

The nuclear power industry is faced with determining what to do with equipment and instrumentation reaching obsolescence and selecting the appropriate approach for upgrading the affected equipment. One of the systems in a nuclear power plant that has been a source of poor reliability in terms of replacement parts and control performance is the reactor recirculation pump speed/ flow control system for boiling water reactors (BWR). All of the operating BWR-3 and BWR-4’s use motor-generator sets, with a fluid coupled speed changer, to control the speed of the recirculation water pumps over the entire speed range of the pumps. These systems historically have had high maintenance costs, relative low efficiency, and relatively inaccurate speed control creating unwanted unit de-rates. BWR-5 and BWR-6 recirculation flow control schemes, which use flow control valves in conjunction with two-speed pumps, are also subject to upgrades for improved performance and reliability. These systems can be improved by installing solid-state adjustable speed drives (ASD), also known as variable frequency drives (VFD), in place of the motor-generator sets and the flow control valves. Several system configurations and ASD designs have been considered for optimal reliability and return on investment. This paper will discuss a highly reliable system and ASD design that is being developed for nuclear power plant reactor recirculation water pump controls. Design considerations discussed include ASD topology, controls architecture, accident, transient and hydraulic analyses, potential reactor internals modifications, installation, demolition and economic benefits.

Development of a digital turbine control system in a nuclear power plant

2009 ◽  
Vol 7 (1) ◽  
pp. 67-73 ◽  
Author(s):  
In-Kyu Choi ◽  
Jong-An Kim ◽  
Chang-Ki Jeong ◽  
Joo-Hee Woo ◽  
Ji-Young Choi ◽  
...  
Keyword(s):  
Control System ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power
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