A deep learning approach to estimate temperature and flow velocity distributions of wire-wrapped fuel assemblies

被引:3
|
作者
Li, Yang [1 ]
Wang, Rongdong [1 ,2 ]
Song, Yuxin [1 ]
Wan, Detao [1 ]
Hu, Dean [1 ]
Jiang, Chao [1 ]
机构
[1] Hunan Univ, Key Lab Adv Design & Simulat Tech Special Equipmen, Minist Educ, Changsha 410082, Peoples R China
[2] China Inst Atom Energy, Dept Reactor Engn Technol Res, Beijing 102413, Peoples R China
基金
中国国家自然科学基金;
关键词
CFD; Deep learning; Wire-wrapped; Sodium-cooled fast reactors; Thermal-hydraulic; FAST-REACTOR FUEL; HEAT-TRANSFER; NUMERICAL-SIMULATION; TURBULENT-FLOW; PIN BUNDLES; SPACER;
D O I
10.1016/j.icheatmasstransfer.2024.107853
中图分类号
O414.1 [热力学];
学科分类号
摘要
Computational fluid dynamic (CFD) of thermal-hydraulic has been widely used to investigate the design of sodium-cooled fast reactors (SFR). However, the specific models for wire-wrapped fuel assemblies in SFR always require complex procedures to set up and expensive computational costs to obtain final simulation results. In this study, we proposed a deep learning-based (DL-based) approach to estimate the temperature and flow velocity distributions of wire-wrapped fuel assemblies. The DL-based approach consists of an Auto-encoder model and Deep neural networks model, which are trained separately through a combination of unsupervised and supervised learning methods. The DL-based model was trained to take the input of external temperature probe values and corresponding boundary conditions and directly output the temperature and flow velocity distributions, bypassing the expensive CFD calculation. The presented DL-based approach can accurately and quickly estimate the temperature, transverse velocity, and axial velocity distributions with average errors of 0.00597%, 0.00506%, and 0.00745%, respectively. To our knowledge, this is the first study that demonstrates the feasibility of using DL as an alternative model to CFD to estimate thermal-hydraulic distributions accurately and quickly in SFR.
引用
收藏
页数:14
相关论文
共 50 条
  • [31] Comparative analysis of flow and convective heat transfer between 7-pin and 19-pin wire-wrapped fuel assemblies
    Raza, Wasim
    Kim, Kwang-Yong
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2008, 45 (07) : 653 - 661
  • [32] Analysis of flow-induced vibration of wire-wrapped fuel assemblies under the liquid metal axial flow in the Gen-IV nuclear reactor
    Guo, Hongjian
    Li, Wei
    Zhang, Jing
    Wu, Yingwei
    Wang, Mingjun
    Qiu, Suizheng
    Tian, Wenxi
    ANNALS OF NUCLEAR ENERGY, 2023, 188
  • [33] FLOW SPLITS AND BOWING PERFORMANCES OF FUEL PINS IN WIRE WRAPPED FBR FUEL ASSEMBLIES.
    Itoh, K.
    Seino, S.
    Kubota, T.
    Transactions of the International Conference on Structural Mechanics in Reactor Technology, 1979, E
  • [34] Static pressure and wall shear stress distributions in air flow in a seven wire-wrapped rod bundle
    Fernandez Y Fernandez, Elói
    Carajilescov, Pedro
    Revista Brasileira de Ciencias Mecanicas/Journal of the Brazilian Society of Mechanical Sciences, 2000, 22 (02): : 291 - 302
  • [35] EXPERIMENTAL CORRELATION OF CROSS-FLOW PRESSURE DROP FOR TRIANGULAR ARRAY WIRE-WRAPPED ROD ASSEMBLIES.
    Suh, Kune Yull
    Todreas, Neil E.
    1600, (76):
  • [36] AN EXPERIMENTAL CORRELATION OF CROSS-FLOW PRESSURE-DROP FOR TRIANGULAR ARRAY WIRE-WRAPPED ROD ASSEMBLIES
    SUH, KY
    TODREAS, NE
    NUCLEAR TECHNOLOGY, 1987, 76 (02) : 229 - 240
  • [37] THREE-DIMENSIONAL FLOW PHENOMENA IN A WIRE-WRAPPED 37-PIN FUEL BUNDLE FOR SFR
    Jeong, Jae-Ho
    Yoo, Jin
    Lee, Kwi-Lim
    Ha, Kwi-Seok
    NUCLEAR ENGINEERING AND TECHNOLOGY, 2015, 47 (05) : 523 - 533
  • [38] THERMAL-STRESS DUE TO CIRCUMFERENTIAL VARIATION OF TEMPERATURE IN THE CLADDING OF WIRE-WRAPPED FUEL BUNDLES OF LMFBR
    KOMODA, S
    IWATA, K
    KINJO, K
    KERNENERGIE, 1990, 33 (11): : 428 - 430
  • [39] DISTRIBUTED PARAMETER ANALYSIS FOR THE PREDICTION OF THE FINE-STRUCTURE OF FLOW AND TEMPERATURE-FIELDS IN WIRE-WRAPPED FUEL PIN BUNDLE GEOMETRIES
    SHIMIZU, T
    NINOKATA, H
    SHISHIDO, H
    NUCLEAR ENGINEERING AND DESIGN, 1990, 120 (2-3) : 369 - 383
  • [40] POROUS BODY MODEL FOR PREDICTING TEMPERATURE DISTRIBUTION IN WIRE-WRAPPED ROD ASSEMBLIES OPERATING IN COMBINED FORCED AND FREE CONVECTION
    KHAN, EU
    ROHSENOW, WM
    SONIN, AA
    TODREAS, NE
    NUCLEAR ENGINEERING AND DESIGN, 1975, 35 (02) : 199 - 211