Measurements of actinide nuclides in water samples from the primary circuit of a nuclear power plant

1981 ◽  
Vol 64 (1-2) ◽  
pp. 55-64 ◽  
Author(s):  
G. Rosner
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Water Samples ◽  
Nuclear Power ◽  
Primary Circuit

14C Distribution in Atmospheric and Aquatic Environments Around Qinshan Nuclear Power Plant, China

Radiocarbon ◽  
2014 ◽  
Vol 56 (3) ◽  
pp. 1107-1114 ◽  
Author(s):  
Zhongtang Wang ◽  
Dan Hu ◽  
Hong Xu ◽  
Qiuju Guo
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Water Samples ◽  
Nuclear Power ◽  
Dissolved Inorganic Carbon ◽  
Tap Water ◽  
Surface Seawater ◽  
Pressurized Water ◽  
Specific Activities ◽  
Water Reactors

Atmospheric CO2 and aquatic water samples were analyzed to evaluate the environmental 14C enrichment due to operation of the Qinshan nuclear power plant (NPP), where two heavy-water reactors and five pressurized-water reactors are employed. Elevated 14C-specific activities (2–26.7 Bq/kg C) were observed in the short-term air samples collected within a 5-km radius, while samples over 5 km were close to background levels. The 14C-specific activities of dissolved inorganic carbon (DIC) in the surface seawater samples ranged from 196.8 to 206.5 Bq/kg C (average 203.4 Bq/kg C), which are close to the background value. No elevated 14C level in surface seawater was found after 20 years of operation of Qinshan NPP, indicating that the 14C discharged was well diffused. The results of the freshwater samples show that excess 14C-specific activity (average 17.1 Bq/kg C) was found in surface water and well water samples, while no obvious 14C increase was found in drinking water (groundwater and tap water) compared to the background level.

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.

Three-Dimensional Profilometry Utilization on VVER Type Reactors

2020 ◽  
Vol 7 (2) ◽  
Author(s):  
Jaroslav Brom ◽  
Jan Patera ◽  
Pavel Zahrádka
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Three Dimensional ◽  
Laser Scanner ◽  
Primary Circuit ◽  
3D Profilometry ◽  
Circuit Components ◽  
3D Profile ◽  
Reactor Pressure

Abstract The paper is focused on the application of three-dimensional (3D) profilometry on water–water energetic reactor (VVER) type nuclear power plant (NPP) equipment. This method is becoming increasingly used in the power industry and replaces conventional methods such as micrometer measurements. One of the greatest benefits is the accurate recording of the 3D profile of the measured surface and the possibility of its comparison with the production documentation or with the results from previous measurements. Centrum Výkumu Řež, s.r.o. (Research Center Řež) uses 3D laser scanner with a measuring arm. This method was, for example, successfully used for reactor pressure vessel (RPV), steam generator (SG), and bolts. The results are used by the NPP operator for the lifetime management of the primary circuit components.

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