Artificial Neural Network Modelling of In-Reactor Diametral Creep of Zr2.5%Nb Pressure Tubes of Indian PHWRs

被引:21
作者
Sarkar, A. [1 ]
Sinha, S. K. [2 ]
Chakravartty, J. K. [1 ]
Sinha, R. K. [3 ]
机构
[1] Bhabha Atom Res Ctr, Mat Grp, Bombay 400085, Maharashtra, India
[2] Bhabha Atom Res Ctr, Reactor Engn Div, Bombay 400085, Maharashtra, India
[3] Anushakti Bhavan, Dept Atom Energy, Bombay 400001, Maharashtra, India
关键词
Pressurized Heavy Water Reactor; Pressure tube; Diametral creep; Artificial Neural Network; PROCESSING PARAMETERS; DEFORMATION; BEHAVIOR; STEELS;
D O I
10.1016/j.anucene.2014.01.043
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
A model is developed to predict the in-reactor diametral creep in the Zr-2.5%Nb pressure tube of Indian Pressurized Heavy Water power reactors (PHWR) using Artificial Neural Network (ANN). The inputs of the neural network are alloy composition of the tube (concentration of Nb, O, N and Fe), mechanical properties (YS, UTS, %EL), temperature and fluence whereas diametral creep rate is the output. Measured diametral creep rate data from the sampled pressure tubes operating in Indian PHWRs at Rajasthan Atomic Power Station (RAPS 2), Kakrapar Atomic Power Station (KAPS 2) and Kaiga Generating Station (KGS) are employed to develop the model. A three-layer feed-forward ANN is trained with Levenberg-Marquardt training algorithm. It has been shown that the developed ANN model can efficiently and accurately predict the diametral creep of pressure tube. Results show the high significance of O concentration and mechanical properties in determining diametral creep rate. (C) 2014 Elsevier Ltd. All rights reserved.
引用
收藏
页码:246 / 251
页数:6
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