Investigation of nuclear power plant behaviour at low power and cold conditions during an overpressurization in primary circuit

2013 ◽  
Vol 62 ◽  
pp. 231-241 ◽  
Author(s):  
Pavlin Groudev ◽  
Marina Andreeva ◽  
Malinka Pavlova
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Low Power ◽  
Nuclear Power ◽  
Primary Circuit ◽  
Plant Behaviour

Fatigue Monitoring in the Context of Long-Term Operation of the Goesgen Nuclear Power Plant Using AREVA’s FAMOSi

2015 ◽  
Author(s):  
Thomas Wermelinger ◽  
Florian Bruckmüller ◽  
Benedikt Heinz
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Primary Circuit ◽  
Feed Water ◽  
Term Operation ◽  
Operation Modes ◽  
Fatigue Monitoring ◽  
Load Evaluation

In the context of long-term operation or lifetime extension most regulatory bodies demand from utilities and operators of nuclear power plants to monitor and evaluate the fatigue of system, structures and components systematically. As does the Swiss Federal Nuclear Safety Inspectorate ENSI. The nuclear power plant Goesgen started its commercial operation in 1979 and will go into long-term operation in 2019. The increased demand for monitoring and evaluating fatigue due to the pending long-term operation led the Goesgen nuclear power plant to expand the scope of their surveillance and therefore to install AREVA’s fatigue monitoring system FAMOSi in the 2014 outage. The system consists of 39 measurement sections positioned at the primary circuit and the feed-water nozzles of the steam generators. The locations were chosen due to their sensitivity for fatigue. The installed FAMOSi system consists of a total of 173 thermocouples which were mounted in order to get the necessary input data for load evaluation. The advantage of FAMOSi is the possibility to obtain real data of transients near places with highest fatigue usage factors. Examples of steam generator feed-in during heating-up and cooling-down will be given. In addition, spray events before and after the installation of closed loop controlled spray valves will be compared. The measurements and the results of the load evaluation are not only of interest for internal use e.g. in regard to optimization of operation modes (e.g. load-following), but must also be reported to ENSI annually. In addition, by evaluation of stresses and determination of usage factors combined with an optimization of operation modes an early exchange of components can be avoided.

Identification of the primary circuit dynamics in a pressurized water nuclear power plant

2008 ◽  
Vol 41 (2) ◽  
pp. 10640-10645
Author(s):  
Csaba Fazekas ◽  
Gábor Szederkényi ◽  
Katalin M. Hangos
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Primary Circuit ◽  
Pressurized Water

scholarly journals Comparison of state feedback and PID control of pressurizer water level in nuclear power plant

2013 ◽  
Vol 23 (4) ◽  
pp. 455-471 ◽  
Author(s):  
Mariusz Czapliński ◽  
Paweł Sokólski ◽  
Kazimierz Duzinkiewicz ◽  
Robert Piotrowski ◽  
Tomasz Rutkowski
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Water Level ◽  
Nuclear Power ◽  
State Feedback ◽  
Reference Value ◽  
Primary Circuit ◽  
Pipeline System ◽  
Level Control ◽  
Pressurized Water

Abstract The pressurizer water level control system in nuclear power plant with pressurized water reactor (PWR) is responsible for coolant mass balance. The main control goal is to stabilize the water level at a reference value and to suppress the effect of time-varying disturbances (e.g. coolant leakage in primary circuit pipeline system). In the process of PWR power plant operation incorrect water level may disturb pressure control or may cause damage to electric heaters which could threaten plant security and stability. In modern reactors standard PID controllers are used to control water level in a pressurizer. This paper describes the performance of state feedback integral controller (SFIC) with reduced-order Luenberger state observer designed for water level control in a pressurizer and compares it to the standard PID controller. All steps from modeling of a pressurizer through control design to implementation and simulation testing in Matlab/Simulink environment are detailed in the paper.

scholarly journals Analysis of Data Collected at Control Room Full Scope Simulator at Dukovany Nuclear Power Plant

2017 ◽  
Vol 12 (2) ◽  
pp. 11-22
Author(s):  
Kateřina Kozlová ◽  
Karla Barčová ◽  
Jan Kubíček
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Computer Program ◽  
Nuclear Power ◽  
Human Factor ◽  
Final Evaluation ◽  
Primary Circuit ◽  
Control Room ◽  
Temporal Passage

Abstract This article describes a computer program that will be used by experts to analyze human factor reliability when analyzing data obtained during the training of operators on a nuclear power plant's control room simulator. The program was applied to data collected during the training of a scenario called Rupture of the Hot Loop of the Primary Circuit (250 t/h). Based on the comparison of charts, temporal passage through the scenario, or by personal participation in the training, analysts evaluate the successful passing of the practice scenario and propose final recommendations. The article also describes the criteria for successfully passing the practiced scenario and its final evaluation.

Sign in / Sign up

Export Citation Format

Share Document