Effect of enrichment of plate-type fuel assembly on fuel performance

被引：0

作者：

Yue Z. ^{[1
,2
]}

He Y. ^{[1
,2
]}

Liu H. ^{[1
,2
]}

Wu Y. ^{[1
,2
]}

Zhang J. ^{[1
,2
]}

Su G. ^{[1
,2
]}

Tian W. ^{[1
,2
]}

Qiu S. ^{[1
,2
]}

机构：

[1] Shaanxi Key Laboratory of Advanced Nuclear Energy and Technology, School of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an

[2] State Key Laboratory of Multiphase Flow in Power Engineering, Xi'an Jiaotong University, Xi'an

来源：

He Jishu/Nuclear Techniques | 2024年 / 47卷 / 06期

关键词：

Fuel performance; Multiphysics coupling; Neutronic physics; Thermal-hydraulics; U[!sub]3[!/sub]Si[!sub]2[!/sub]-Al fuel;

D O I：

10.11889/j.0253-3219.2024.hjs.47.060606

中图分类号：

学科分类号：

摘要：

[Background] The enrichment of nuclear fuel may significantly influence the fuel performance of a reactor. [Purpose] This study aims to explore the effect of U3Si2-Al plate-type fuel enrichment on its performance, [Methods] The fuel performance analysis code BEEs-Plates, neutronics Monte Carlo code OpenMC, and the one-dimensional system analysis code ZEBRA were coupled together within the MOOSE (Multiphysics Object-Oriented Simulation Environment) framework. Then the coupling code was employed to conduct the multiphysics coupling calculation for JRR-3 (Japanese Research Reactor No.3) fuel assembly enriched at 15%, 20%, and 25%. The data exchange among the three codes were realized with the help of interpolation transfer method implemented in MOOSE. Additionally, neutron physical parameters and fuel performance parameters after 231 d of operation were analyzed when the average fuel consumption of the module was 125.71 GWd∙tU-1. [Results] The calculation results indicate that the max power density of fuel assembly enriched at 25% is 18% higher than the assembly enriched at 15%. Due to the high thermal conductivity of aluminum, the temperature difference in the fuel assembly is almost negligible whilst there is a significant difference in the fast neutron fluence. The results of fuel temperature and fast neutron fluence show that the volumetric strain is more obviously affected by the fuel temperature. Specifically, the plastic strain of the assembly with 25% enrichment is approximately 40% higher than that of the assembly with 15% enrichment. [Conclusion] The analysis results of this study suggest that the assembly with a higher enrichment is more prone to failure. © 2024 Science Press. All rights reserved.

引用

共 26 条

[1] Gaston D R, Permann C J, Peterson J W, Et al., Physics-based multiscale coupling for full core nuclear reactor simulation[J], Annals of Nuclear Energy, 84, pp. 45-54, (2015)
[2] Kouchunas B, Jabaay D, Downar T, Et al., Validation and application of the 3D neutron transport MPACT within CASL VERA-CS, (2015)
[3] Yu J K, Lee H, Lemaire M, Et al., MCS based neutronics/thermal-hydraulics/fuel-performance coupling with CTF and FRAPCON[J], Computer Physics Communications, 238, pp. 1-18, (2019)
[4] Xu X B, Liu Z Y, Wu H C, Et al., Neutronics/thermal-hydraulics/fuel-performance coupling for light water reactors and its application to accident tolerant fuel, Annals of Nuclear Energy, 166, (2022)
[5] YU Ganglin, WANG Kan, Research on fuel physical characteristics in small long-life nuclear power system[J], Nuclear Power Engineering, 28, 4, pp. 5-8, (2007)
[6] Deng C Q, He Y N, Xiang F R, Et al., Finite element based fuel performance investigation of U3Si2-FeCrAl design under normal and RIA conditions, Progress in Nuclear Energy, 149, (2022)
[7] He Y N, Chen P, Wu Y W, Et al., Preliminary evaluation of U3Si2-FeCrAl fuel performance in light water reactors through a multi-physics coupled way, Nuclear Engineering and Design, 328, pp. 27-35, (2018)
[8] He Y N, Niu Y H, Xiang F R, Et al., Preliminary development of a multi-physics coupled fuel performance code for annular fuel analysis under normal conditions, Nuclear Engineering and Design, 393, (2022)
[9] He Y N, Shirvan K, Wu Y W, Et al., Fuel performance optimization of U3Si2-SiC design during normal, power ramp and RIA conditions, Nuclear Engineering and Design, 353, (2019)
[10] Xiang F R, He Y N, Niu Y H, Et al., A new method to simulate dispersion plate-type fuel assembly in a multiphysics coupled way, Annals of Nuclear Energy, 166, (2022)

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