Research on Adaptive BP Neural Network Prediction Method for Thermal Parameters of China Experimental Fast Reactor

被引:0
|
作者
Wang D. [1 ]
Yang H. [1 ]
Wang D. [1 ]
Lin C. [1 ]
Wang W. [3 ]
机构
[1] Division of Reactor Engineering Technology Research, China Institute of Atomic Energy, Beijing
[2] Graduate School of China National Nuclear Corporation, Beijing
[3] Southwestern Institute of Physics, Chengdu
关键词
Adaptive method; BP neural network; China Experimental Fast Reactor; Maximum temperature of fuel cladding;
D O I
10.7538/yzk.2019.youxian.0751
中图分类号
学科分类号
摘要
Whether the thermal-hydraulic parameters of China Experimental Fast Reactor (CEFR) core exceed the limit is the standard for evaluating the safe operation of the reactor. For the maximum temperature prediction problem of fuel cladding, after generating the data samples by the core sub-channel analysis code COBRA, an intelligent prediction code based on adaptive BP neural network algorithm was developed in the paper. For a specific single-box component, only the core inlet power and mass flow rate were required to achieve fast and accurate prediction of the fuel cladding maximum temperature. Compared with COBRA, in the scenario of large-scale repetitive calculation, self development code can save a lot of calculation time and rescource, and improve the operating efficiency of fuel cladding design and CEFR operation. The experimental analysis shows that the maximum relative error of BP neural network method is less than 6%, the average prediction relative error is less than 3%, and the calculation efficiency is improved to 300 times of the original code. So the prediction accuracy of the network model is high, and self development code is easy to apply to other parameter predictions of the experimental fast reactor. © 2020, Editorial Board of Atomic Energy Science and Technology. All right reserved.
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页码:1809 / 1816
页数:7
相关论文
共 15 条
  • [1] (2007)
  • [2] 9, pp. 20-23
  • [3] HE Jiarun, GUO Zhengrong, Summary of development of sodium cooled fast reactor, Dongfang Electric Review, 27, 107, pp. 36-43, (2013)
  • [4] ZHOU Zhiwei, YANG Hongyi, LI Song, Et al., Primary development of thermal-hydraulics design code for CFR600 core, Atomic Energy Science and Technology, 52, 1, pp. 56-63, (2018)
  • [5] YU Jiyang, JIA Baoshan, Scheme design of passive residual heat removal system for reactor, Chinese Journal of Nuclear Science and Engineering, 23, 1, pp. 32-38, (2003)
  • [6] JIAO Zhiqin, Principle and application of BP artificial neural network, Science and Technology Wind, 12, pp. 206-207, (2010)
  • [7] HUO Xiaodong, XIE Zhongsheng, Research on application of genetic algorithm in fuel management of CANDU reactor, Nuclear Power Engineering, 26, 6, pp. 539-543, (2005)
  • [8] YU Zhixiang, ZOU Shuliang, XU Shoulong, Et al., Study on fast calculation function of marine reactor shielding design based on BP neural network, Nuclear Electronics & Detection Technology, 36, 2, pp. 209-213, (2016)
  • [9] pp. 272-295, (1999)
  • [10] XUE Xiuli, YANG Hongyi, YANG Fuchang, Et al., Numerical simulation of steady state thermal engineering at the outlet of CEFR core fuel zone, Chinese Journal of Nuclear Science and Engineering, 28, 1, pp. 75-80, (2008)