An intelligent approach for thermal-hydraulic studies on safety and efficiency of nuclear power plant

被引:2
作者
Hossain, Altab [1 ]
Islam, Shakerul [1 ]
Hossain, Tanvir [1 ]
Salahuddin, Abu Zafar Mohammad [1 ]
Sarkar, Abdur Rashid [1 ]
机构
[1] Mil Inst Sci & Technol, Dept Nucl Sci & Engn, Dhaka 1216, Bangladesh
来源
2ND INTERNATIONAL CONFERENCE ON ENERGY AND POWER (ICEP2018) | 2019年 / 160卷
关键词
Nuclear power plant; reactor thermal-hydraulic; fuzzy-expert system; heat transfer; safety function; PERFORMANCE;
D O I
10.1016/j.egypro.2019.02.178
中图分类号
TE [石油、天然气工业]; TK [能源与动力工程];
学科分类号
0807 ; 0820 ;
摘要
An effective identification of breakdowns is of premier importance for the safe and reliable operation of Nuclear Power Plants (NPP). The potential consequences of several terrorized activities may harm the society using nuclear and its associated facilities by using faulty components. Subsequently, rigorous nuclear reactor thermal-hydraulic experimental events support design improvement which are important vectors to be considered in nuclear safety measures. To challenge this problem, a number of linear and nonlinear pattern recognition methods have been utilized. Therefore, the aim of the present work is to study the application of fuzzy expert system (FES) model on a complex system such as nuclear reactor thermal-hydraulic system and their adaptation for the early forecast of irregular behaviour. The purpose of this study is to examine the relationship between reactor design parameters, in particular safety function areas of heat removal capability, conductivity of cladding, convective heat transfer characteristics of coolant and their impact of severity, and to illustrate how fuzzy expert system might play an important role in assessment of risk. Several simulation cases are conducted for evaluating the performance of the present diagnosis system. The simulation results show the good performance of the present intelligent approach in thermal-hydraulic studies on safety and efficiency of NPP. (C) 2019 The Authors. Published by Elsevier Ltd.
引用
收藏
页码:436 / 442
页数:7
相关论文
共 11 条
[1]  
Cacuci Dan Gabriel, 1986, NUCL SCI ENGENEERING, V93, P111
[2]   Fast Reactor Development in the United States [J].
Cochran, Thomas B. ;
Feiveson, Harold A. ;
von Hippel, Frank .
SCIENCE & GLOBAL SECURITY, 2009, 17 (2-3) :109-131
[3]   Fuzzy evaluation for an intelligent air-cushion tracked vehicle performance investigation [J].
Hossain, Altab ;
Rahman, Ataur ;
Mohiuddin, A. K. M. .
JOURNAL OF TERRAMECHANICS, 2012, 49 (02) :73-80
[4]  
Ibrahim S. J., 2013, Leonardo Electron. J. Practices Technol., V12, P93
[5]  
Karthigaivel R., 2014, INT J APPL ENG RES, V9, P30605
[6]   Prediction of heat transfer performance of CuO/water nanofluids flow in spirally corrugated helically coiled heat exchanger using fuzzy logic technique [J].
Khairul, M. A. ;
Hossain, A. ;
Saidur, R. ;
Alim, M. A. .
COMPUTERS & FLUIDS, 2014, 100 :123-129
[7]  
Kotb SA, 2016, ARAB J NUCL SCI APPL, V49, P85
[8]   Limitations of Nuclear Power as a Sustainable Energy Source [J].
Pearce, Joshua M. .
SUSTAINABILITY, 2012, 4 (06) :1173-1187
[9]  
Razavi-Far Roozbeh, 2009, International Journal of Nuclear Knowledge Management, V3, P296, DOI 10.1504/IJNKM.2009.027063
[10]  
Velmurugan S., 2016, NPC INT C