Research on Data-Driven Methods for Solving High-Dimensional Neutron Transport Equations
Author:
Peng Zhiqiang123, Lei Jichong123ORCID, Ni Zining123, Yu Tao13, Xie Jinsen13, Hong Jun2, Hu Hong2
Affiliation:
1. School of Nuclear Science and Technology, University of South China, Hengyang 421001, China 2. School of Safe and Management Engineering, Hunan Institute of Technology, Hengyang 421002, China 3. Key Lab of Advanced Nuclear Energy Design and Safety, Ministry of Education, Hengyang 421001, China
Abstract
With the continuous development of computer technology, artificial intelligence has been widely applied across various industries. To address the issues of high computational cost and inefficiency in traditional numerical methods, this paper proposes a data-driven artificial intelligence approach for solving high-dimensional neutron transport equations. Based on the AFA-3G assembly model, a neutron transport equation solving model is established using deep neural networks, considering factors that influence the neutron transport process in real engineering scenarios, such as varying temperature, power, and boron concentration. Comparing the model’s predicted values with reference values, the average error in the infinite multiplication factor kinf of the assembly is found to be 145.71 pcm (10−5), with a maximum error of 267.10 pcm. The maximum relative error is less than 3.5%, all within the engineering error standards of 500 pcm and 5%. This preliminary validation demonstrates the feasibility of using data-driven artificial intelligence methods to solve high-dimensional neutron transport equations, offering a new option for engineering design and practical engineering computations.
Funder
National Natural Science Foundation of China Hunan Provincial Department of Education Key Teaching Reform Project
Reference24 articles.
1. Nuclear physics B. Nuclear dynamics, theoretical;Bethe;Rev. Mod. Phys.,1937 2. Ren, C., He, L., Lei, J., Liu, J., Huang, G., Gao, K., Qu, H., Zhang, Y., Li, W., and Yang, X. (2023). Neutron transport calculation for the BEAVRS core based on the LSTM neural network. Sci. Rep., 13. 3. Lei, J., Xie, J., Chen, Z., Yu, T., Yang, C., Zhang, B., Zhao, C., Li, X., Wu, J., and Zhuang, H. (2021). Validation of Doppler Temperature Coefficients and Assembly Power Distribution for the Lattice Code KYLIN V2.0. Front. Energy Res., 9. 4. Validation of the SHNC time-dependent transport code based on the spherical harmonics method for complex nuclear fuel assemblies;Capilla;J. Comput. Appl. Math.,2020 5. Marvin: A parallel three-dimensional transport code based on the discrete ordinates method for reactor shielding calculations;Zhang;Prog. Nucl. Energy,2021
|
|