Reliability data update method for emergency diesel generator of Daya Bay Nuclear Power Plant

2011 ◽  
Vol 38 (11) ◽  
pp. 2575-2580 ◽  
Author(s):  
Muhammad Zubair ◽  
Zhang Zhijian
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Daya Bay ◽  
Diesel Generator ◽  
Reliability Data ◽  
Data Update

Diesel Generator Equipment Diagnostics of Nuclear Power Plant Using Deterministic and Stochastic Methods

2016 ◽  
Vol 20 (3) ◽  
pp. 74-79
Author(s):  
E.A. Abidova ◽  
L.S. Hegay ◽  
A.V. Chernov ◽  
V.A. Bulava ◽  
O.Yu. Pugachyova ◽  
...  
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Stochastic Methods ◽  
Diesel Generator

Dynamic Simulation Studies of Performed Additional Tests During FAT for Emergency Diesel Generators at Nuclear Power Plant

2016 ◽  
Author(s):  
Salah K. Kanaan ◽  
Amer Omanovic
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Electric Circuit ◽  
Diesel Generator ◽  
Safety Regulations ◽  
Auxiliary Power ◽  
Current Voltage ◽  
Measurement Results ◽  
Generator Sets

In 2004, a decision was made to perform a modernization and a new power uprate of unit 2 at Oskarshamn nuclear power plant in Sweden. Among the most important reasons for this decision were new safety regulations from Swedish Radiation Safety Authority and ageing of important components. A project was established and became the largest nuclear power modernization in the world. The modernization led to the need of analysing the auxiliary power system to ensure that it could supply the unit after the uprate, given tolerances on current, voltage and frequency. During the process of developing models for the diesel generator sets, it turned out that the suppliers could not deliver enough satisfactory material for modelling the diesel engines, the speed controllers and the magnetization systems. Therefore, Oskarshamn nuclear power plant with the help of the manufacturers of the diesel generator sets carried out additional measurements in order to collect data for modelling. Based on electric circuit diagrams provided by the manufacturers, block diagrams of the magnetization systems were made. For the speed controllers, no information was available at all so it was assumed that the controller was of PI-type. The parameters of the magnetization systems and the speed controllers were then tuned using the measurement results. Finally, a comparison between simulated results and the measurement results were made, showing good agreement. This is especially true in the most commonly used operating interval of the diesel generator sets.

U.S. Nuclear Power Plant Performance Assessment Using the Versatile Economic Risk Tool (VERT)

2021 ◽  
Author(s):  
Jaden C. Miller ◽  
Spencer C. Ercanbrack ◽  
Chad L. Pope
Keyword(s):  
Risk Assessment ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Fault Tree ◽  
Plant Performance ◽  
Economic Risk ◽  
Reliability Data ◽  
Water Reactor ◽  
Tree Models

Abstract This paper addresses the use of a new nuclear power plant performance risk analysis tool. The new tool is called Versatile Economic Risk Tool (VERT). VERT couples Idaho National Laboratory’s SAPHIRE and RAVEN software packages. SAPHIRE is traditionally used for performing probabilistic risk assessment and RAVEN is a multi-purpose uncertainty quantification, regression analysis, probabilistic risk assessment, data analysis and model optimization software framework. Using fault tree models, degradation models, reliability data, and economic information, VERT can assess relative system performance risks as a function of time. Risk can be quantified in megawatt hours (MWh) which can be converted to dollars. To demonstrate the value of VERT, generic pressurized water reactor and boiling water reactor fault tree models were developed along with time dependent reliability data to investigate the plant systems, structures, and components that impacted performance from the year 1980 to 2020. The results confirm the overall notion that US nuclear power plant industry operational performance has been improving since 1980. More importantly, the results identify equipment that negatively or positively impact performance. Thus, using VERT, individual plant operators can target systems, structures, and components that merit greater attention from a performance perspective.

scholarly journals Human Reliability Studies With Microworld Simulators

2019 ◽  
Vol 63 (1) ◽  
pp. 1829-1833 ◽  
Author(s):  
Ronald Boring ◽  
Thomas Ulrich ◽  
Roger Lew ◽  
Martin Rasmussen Skogstad
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Data Collection ◽  
Nuclear Power ◽  
Human Error ◽  
Data Sources ◽  
Human Reliability ◽  
Reliability Data ◽  
Experimental Control ◽  
Advantages And Disadvantages

The authors have recently developed a microworld, a simplified process control simulator, to simulate a nuclear power plant. The microworld provides an environment that can be readily manipulated to gather data using a range of participants, from students to fully qualified operators. Because the microworld represents a simplified domain, it is possible to have more precise experimental control compared with the complex and confounding environment afforded by a full-scope simulator. In this paper, we discuss collecting human reliability data from a microworld. We review the generalizability of human error data from the microworld compared to other data sources like full-scope simulator studies and compare advantages and disadvantages of microworld simulator studies to support human reliability data collection needs.

Attitudes of Hong Kong residents toward the Daya Bay nuclear power plant

Energy Policy ◽  
2013 ◽  
Vol 62 ◽  
pp. 1172-1186 ◽  
Author(s):  
William Chung ◽  
Iris M.H. Yeung
Keyword(s):  
Hong Kong ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Daya Bay
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