scholarly journals A Correlation-Based Feature Selection Algorithm for Operating Data of Nuclear Power Plants

2021 ◽  
Vol 2021 ◽  
pp. 1-15
Author(s):  
Yuxuan He ◽  
Hongxing Yu ◽  
Ren Yu ◽  
Jian Song ◽  
Haibo Lian ◽  
...  
Keyword(s):  
Feature Selection ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Dimensionality Reduction ◽  
Nuclear Power ◽  
Selection Algorithm ◽  
Feature Selection Algorithm ◽  
Operating Data ◽  
Comparison Results ◽  
Correlation Based Feature Selection

Nuclear power plant operating data are characterized by a large variety, strong coupling, and low data value density. When using machine learning techniques for fault diagnosis and other related research, feature selection enables dimensionality reduction while maintaining the physical meaning of the original features, thus improving the computational efficiency and generalization ability of the learning model. In this paper, a correlation-based feature selection algorithm is developed to implement feature selection of nuclear power plant operating data. The proposed algorithm is verified by experiments and compared with traditional correlation-based feature selection algorithms. The experiments and comparison results show that the proposed algorithm is effective in realizing the dimensionality reduction of nuclear power plant operating data.

The Analysis and Realization of Interpreter Language in Nuclear Industry

2014 ◽  
Vol 989-994 ◽  
pp. 2097-2100
Author(s):  
Zheng Zhang ◽  
Hai Bo He ◽  
Hao Liang Lu
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Semantic Analysis ◽  
Reactor Core ◽  
Nuclear Industry ◽  
Logical Language ◽  
Grammatical Analysis ◽  
Actual Operating ◽  
Comparison Results

In order to satisfy the calculation requirements of nuclear power plant operating in different conditions, the integration and combination of reactor core computation modules have been proposed. By writing logical language instructions, and then read by interpreter, the engineering designers can make grammatical analysis, lexical analysis, semantic analysis and information extraction. In Linux system environment, the interpreter can fulfill computational tasks based on the actual operating parameters of nuclear power plant. The comparison results indicate that the calculated results obtained by the interpreter language are correct. Therefore, it also demonstrates that the interpreter language is valid.

A Novel Feature Extraction Scheme for NPP Initiating Event Identification

2016 ◽  
Author(s):  
Ting-Han Lin ◽  
Shun-Chi Wu ◽  
Hwai-Pwu Chou
Keyword(s):  
Feature Extraction ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Dimensionality Reduction ◽  
Nuclear Power ◽  
Sensor Data ◽  
Intrinsic Structure ◽  
Event Identification ◽  
Extraction Scheme ◽  
Discriminant Information

A novel two-stage feature extraction scheme is proposed in this paper for eliciting discriminant information contained in the data from various nuclear power plant (NPP) sensors to facilitate event identification. Based on the idea of sensor type-wise block projection, the primal features can be extracted without losing the intrinsic structure contained in the multi-sensor data. The features are then subject to further dimensionality reduction by selecting the sensors that are most relevant to the events under consideration. Results from detailed experiments with data generated from a simulator of Taiwan Maanshan NPP illustrate the efficacy of the proposed scheme.

scholarly journals Determination of the boron concentration of OPR 1000 reactor critical state using the Cosi OPR1000 system

2016 ◽  
Vol 19 (4) ◽  
pp. 241-248
Author(s):  
Son An Nguyen ◽  
Nguyen Trung Tran ◽  
Tuan Quoc Tran ◽  
Cuong Quang Ly ◽  
Lan Thi Ha Le ◽  
...  
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Critical State ◽  
Nuclear Power ◽  
Boron Concentration ◽  
Nuclear Fission ◽  
Bisection Method ◽  
Control Rod ◽  
Operating Data

In the operation of a nuclear power plant (NPP), to adjust the capacity of NPP is necessary. When the NPP capacity is changed the nuclear fission is also changed. The methods used in changing the capacity of NPP include: changing the boron concentration, changing the position of the control rod groups, and changing the boron concentrations and the position of the control rod groups together. This report presents some results of the research, measurement boron concentrations when nuclear power plans OPR1000 critically state in the cases of ARO, ARI SB, ARI R1, R5 = 191 cm on the basis of the bisection method in the boron concentrations adjustment. The experiment is performed on core the simulator for OPR 1000 nuclear power plant. The results in the 4 cases were similar with NPP operating data using OPR1000 reactor.

scholarly journals Hidden Anomalies Detection in Large Arrays of Nuclear Power Plant Operating Data

2018 ◽  
Vol 3 (3) ◽  
pp. 379
Author(s):  
Chelebiev R.A. ◽  
Skomorokhov A.O.
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Control Systems ◽  
Regression Models ◽  
Nuclear Power ◽  
Economic Losses ◽  
Linear Regression Models ◽  
Coolant Pump ◽  
Operating Data ◽  
Kalinin Npp

In this paper, it is investigated nuclear power plant operating data which was obtained from reactor main coolant pumps (MCP) of the third isolated generating plant of Kalinin NPP. It is necessary permanent monitoring for state of all pump components since breakdown of a reactor coolant pump leads to substantial economic losses. It is installed over 50 sensors of different control systems at the every MCP. Received data is stored but it is not analysed for the purpose of discovering  joint dependencies between equipment pieces and unobvious, hidden trends of accident propagation. In this work, it was proposed techniques for detection of hidden anomalies and MCP operating regularity based on factor analysis, clustering and linear regression models. It was written a Python script which automates necessary calculations.

Preliminary Discussion on Comparison and Analysis on Nuclear Power Plant Materials Standards of ASME and RCC-M

2010 ◽  
Author(s):  
Dong Ning ◽  
Yongdong Wang ◽  
Hui Li ◽  
Zhanggen Bao
Keyword(s):  
Fracture Toughness ◽  
Stainless Steel ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Plant Materials ◽  
Comparison Results ◽  
Layout Structure ◽  
Asme Code ◽  
Comparison And Analysis

This paper is to compare the sections on materials between ASME-BVC and RCC-M code. This paper states the layout structure and the content about NPP materials specified in the two codes and shows the comparison results. This paper emphasizes particularly on the basic differences between two codes; ASME code focuses on fracture toughness requirements for pressure-retaining ferrite materials and RCC-M code focuses on Susceptibility to intergranular corrosion for austenitic and austenitic-ferrite stainless steel.

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