The Application of AFAL Methodology in Substantiation of Instrument Calibration Intervals Extension in Nuclear Power Plant

2013 ◽  
Author(s):  
Ping Zhou ◽  
Xiajun Xu ◽  
Caiqing Tu
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Fuel Cycle ◽  
Calibration Data ◽  
Tolerance Interval ◽  
Sample Number ◽  
Instrument Calibration ◽  
Interval Extension ◽  
Calibration Interval

This is an Introduction about the AFAL methodology of study the instrument drift characteristics, and the application of AFAL in substantiation of instrument calibration interval extension in nuclear power plant. AFAL methodology main aspects include collecting historical instrument calibration data of nuclear power plant, calculating statistics values such as: sample number, mean, median, standard deviation, then work out the drift tolerance interval of the instrument. Based on analysis of these statistical calculated values, will understand the instrument drift performance. This article also discusses technical issues associated with the application of AFAL and how to solve them, such as: grouping instrument, sample sizes, outliers detecting and processing, high-confidence deduction etc. Through the study of the instrument drift characteristics, evaluate the performance of instrument, determine the calibration interval can prolong properly. The application practices of AFAL methodology show, extending instrument calibration interval can support nuclear power plant to achieve the goal of prolonging the fuel cycle, under the nuclear safety precondition. The nuclear power plant can improve the capacity factor of the unit and economic performance.

The Development and Innovation of Spent Fuel Reprocessing in Fuel Cycle

2010 ◽  
Author(s):  
Guang Jun Chen ◽  
Yu Lin Cui ◽  
Guo Guo Zhang ◽  
Hong Jun Yao
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Fuel Cycle ◽  
Fission Products ◽  
Purex Process ◽  
Spent Fuel ◽  
Spent Fuel Reprocessing ◽  
Long Life ◽  
Fuel Reprocessing

With an increased population and an increasing demand for power, nuclear power has attracted an increasing attention and mass nuclear power plant have been built in different countries in the past several decades. At present, about ten thousands ton spent fuels are discharged from nuclear power plant every year and the estimated capacity will approximately add up to 5×105 ton. Therefore, spent fuel reprocessing, by which the co-extraction and separation as well as purification of Uranium and Plutonium could be realized and ensure the recycle of uranium resources and the management of nuclear waste, is a vital step in nuclear fuel cycle including two major strategies, i.e. once-through cycle and closed fuel cycle. It is worth noting that the utilization of MOX fuel made by plutonium mixed with uranium has been successfully achieved in thermal reactor. Fortunately, the middle experiment plant of china spent fuel reprocessing has been being debugged and will be operated completely in future two years. Various reprocessing schemes have been proposed for the extraction of actinides from fission products and other elements presented in spent nuclear fuel. However, after numerous studies of alternate reprocessing methods and intensive searches for better solvents, the PUREX process remains the prime reprocessing method for spent nuclear fuels throughout the world. High burning and strong radioactive spent fuel resulting from the evolution of various reactors drive the development of the advanced PUREX technology, which emphasizes the separation of neptunium and technetium besides the separation of the Uranium and Plutonium from the majority of highly active fission products. In addition, through Partitioning and Transmutation method, some benefits such as segregating the actinides and long life fission products from the high level waste can be obtained. The GANEX process exploited by CEA, which roots in COEX process belonged to advanced PUREX process, considers the separation of the actinides and long life fission products. The study on the pyro-chemical processing such as the method of electro-deposition from molten salts has still not replaced the traditional PUREX process due to various reasons. In conclusion, the future PUREX process will focus on the modified process including predigesting the technical flowsheets and reducing reprocessing costs and using salt-less reagent in order to minimize the waste production.

Instrument Calibration in the Nuclear Power Plant Refueling Cycle Extension Project

2013 ◽  
Author(s):  
Yugui Wang
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Phase Ii ◽  
Economic Benefit ◽  
Nuclear Power ◽  
Primary Method ◽  
Instrument Calibration ◽  
Extension Period

Nuclear power plant refueling cycle extension is an effective way of nuclear power plant to improve economic benefit. This paper, about the Qinshan Nuclear Power Plant phase II 1&2 unit, combination the practical refueling period experience of 12 months refueling period was extended to 18 months, focus on the instrument calibration extension methods of the refueling cycle extension project. Instrument in nuclear power plant running plays very important role, various instruments in the extension period after extended whether their properties still remain available and reliable, require detailed and reliable demonstration. Considering the Qinshan Phase II instrument equipments are purchased from multinational nations and different manufacturers, in this paper, the various demonstration methods are analyzed and compared, from all these methods, we chose the best one as the primary method in the actual demonstration, and use the others as supplemented methods by the demonstration strategies, and the main methods are detailed in the description and examples, so these can ensure that the instrument refueling cycle extension strategy is reliability.

Fuzzy multi-objective decision making approach for nuclear power plant installation

2020 ◽  
Vol 39 (5) ◽  
pp. 6339-6350
Author(s):  
Esra Çakır ◽  
Ziya Ulukan
Keyword(s):  
Linear Programming ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Energy Supply ◽  
Energy Demand ◽  
Nuclear Power ◽  
Power Plants ◽  
Total Duration ◽  
Objective Functions ◽  
Multi Objective

Due to the increase in energy demand, many countries suffer from energy poverty because of insufficient and expensive energy supply. Plans to use alternative power like nuclear power for electricity generation are being revived among developing countries. Decisions for installation of power plants need to be based on careful assessment of future energy supply and demand, economic and financial implications and requirements for technology transfer. Since the problem involves many vague parameters, a fuzzy model should be an appropriate approach for dealing with this problem. This study develops a Fuzzy Multi-Objective Linear Programming (FMOLP) model for solving the nuclear power plant installation problem in fuzzy environment. FMOLP approach is recommended for cases where the objective functions are imprecise and can only be stated within a certain threshold level. The proposed model attempts to minimize total duration time, total cost and maximize the total crash time of the installation project. By using FMOLP, the weighted additive technique can also be applied in order to transform the model into Fuzzy Multiple Weighted-Objective Linear Programming (FMWOLP) to control the objective values such that all decision makers target on each criterion can be met. The optimum solution with the achievement level for both of the models (FMOLP and FMWOLP) are compared with each other. FMWOLP results in better performance as the overall degree of satisfaction depends on the weight given to the objective functions. A numerical example demonstrates the feasibility of applying the proposed models to nuclear power plant installation problem.

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