Effect of Irradiation Creep on Hydrogen-pick-up Induced Multi-field Coupling Behavior in Zircaloy Cladding Tube

被引:0
作者
Wang B.-Z. [1 ]
Ding S.-R. [1 ]
Chen L. [2 ]
Li W.-J. [2 ]
Pang H. [2 ]
机构
[1] Institute of Mechanics and Computational Engineering, Department of Aeronautics and Astronautics, Fudan University, Shanghai
[2] Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu
来源
Yuanzineng Kexue Jishu/Atomic Energy Science and Technology | 2017年 / 51卷 / 09期
关键词
Hydrogen-pick-up; Irradiation creep; Multi-field coupling; Zircaloy cladding tube;
D O I
10.7538/yzk.2017.51.09.1625
中图分类号
学科分类号
摘要
With the irradiation effects considered, the differential governing equations were improved for hydrogen diffusion, hydride precipitation and thermo-mechanical coupling behavior in zircaloy cladding tubes. Based on the corresponding equivalent integral weak forms for the multi-physics fields together with the developed coupling computational methods, the multi-field coupling finite element procedures were generated with the written files on FEPG platform, and they were verified. The effects of irradiation creep on the in-pile multi-field coupling behavior evolution in zircaloy cladding tubes were computed and analyzed. The results indicate that irradiation creep results in stress relaxation in the cladding tubes, which can significantly decrease the Von-Mises stresses, and simultaneous irradiation creep turns the negative hydrostatic stresses into positive ones. Compared with the results without considering irradiation creep, it can be found that irradiation creep will increase the absolute value of negative hydrostatic pressures and the outward hydrostatic stress gradients where the local mechanical interaction occurs between the fuel pellet and the cladding tube, leading to the decrease of hydrogen concentration there, and the increase of hydrogen concentration in the surrounding areas. © 2017, Editorial Board of Atomic Energy Science and Technology. All right reserved.
引用
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页码:1625 / 1632
页数:7
相关论文
共 12 条
[1]  
Jernkvist L.O., Massih A.R., Multi-field modelling of hydride forming metals, Part I: Model formulation and validation, Computational Materials Science, 85, pp. 363-382, (2014)
[2]  
Puls M.P., The Effect of Hydrogen and Hydrides on the Integrity of Zirconium Alloy Components: Delayed Hydride Cracking, (2012)
[3]  
Varias A.G., Massih A.R., Simulation of hydrogen embrittlement in zirconium alloys under stress and temperature gradients, Journal of Nuclear Materials, 279, 2, pp. 273-285, (2000)
[4]  
Sun C., Tan J., Ying S., Et al., Study of the critical temperature for delayed hydride cracking in N18 Zirconium alloy, Acta Metallurgica Sinica, 45, 5, pp. 541-546, (2009)
[5]  
Gou Y., Li Y., Chen H., Et al., Evaluation of a delayed hydride cracking in Zr-2.5Nb CANDU and RBMK pressure tubes, Nuclear Power Engineering, 25, 5, pp. 439-443, (2004)
[6]  
Dai X., Zhao W., Effects of medium on SCC behavior of N18 Zirconium alloy, Materials Research and Application, 3, 1, pp. 37-43, (2009)
[7]  
Siefken L.J., Coryell E.W., Harvego E.A., Et al., MATPRO: A library of materials properties for light-water-reactor accident analysis, (2001)
[8]  
Chen X., Bai X., Xue X., Effects of irradiation damage on electrochemical property of zircaloys, Rare Metal Materials and Engineering, 32, 5, pp. 321-325, (2003)
[9]  
Macdonald P.E., Thompson L.B., MATPRO: A Handbook of Materials Properties for Use in the Analysis of Light Water Reactor Fuel Rod Behavior, (1976)
[10]  
Huang J.H., Huang S.P., Effect of hydrogen contents on the mechanical properties of zircaloy-4, Journal of Nuclear Materials, 208, 1, pp. 166-179, (1994)