Study on frictional behavior of SiCf/SiC composite clad tube clamping condition under nuclear irradiation

Author:

Xiao Chenglong,Shen Liangliang,Zhu Tianqi,Tang Jianbo,Xie Ximing,Fan Xinyu,Xu Jian,Ren Zhiying

Abstract

AbstractSilicon carbide fiber reinforced silicon carbide matrix (SiCf/SiC) composite is the key cladding material of nuclear fuel, which determines the safety and reliability of nuclear fuel storage and transportation. The replacement of its storage and transportation scenario needs to be completed by the manipulator, but the application of SiCf/SiC wear, fracture, and nuclear leakage in the snatching process of brittle-flexible-rigid contact in the irradiation environment has been seriously restricted due to unclear understanding of the damage mechanism. Therefore, the effects of irradiation dose and clamping load on the friction characteristics of the contact interface between SiCf/SiC clad tube are studied in this paper, and the effects of irradiation parameters and clamping force on the static friction coefficient of the contact interface between the clad tube and flexible nitrile are obtained. Based on the Greenwood-Williamson tribological model, a numerical model of the shape and structure of the contact micro-convex at the micro-scale of the clamping interface is constructed by introducing the multi-surface integral, and finally verified by experiments. The research results show that there is a unique “Irradiation suppression zone” under the clamping condition of SiCf/SiC cladding tube under the nuclear irradiation environment, and the growth of static friction coefficient slows down until stagnates after irradiation reaches a certain extent (600 kGy), and there will be a decline when the irradiation dose continues to increase, among which the clamping force of 15.2 N within the irradiation interval of 1,000 kGy can meet the safety of nuclear environment operation. The results of this paper can provide an important theoretical basis and application guidance for the safe operation of SiCf/SiC cladding tubes in the storage and transportation clamping process.

Publisher

Springer Science and Business Media LLC

Subject

Surfaces, Coatings and Films,Mechanical Engineering

Reference40 articles.

1. Kim W J, Kim D, Park J Y. Fabrication and material issues for the application of SiC composites to LWR fuel cladding. NuclEng Technol 45(4): 565–572 (2013)

2. Wang P, Liu F, Wang H, Li H, Gou Y. A review of third generation SiC fibers and SiCj/SiC composites. J Mater Sci Technol 35(12): 2743–2750 (2019)

3. Wang C S. Research progress in application of Cf/SiC composites. J Mater Sci Technol 25(3): 489–492 (2007)

4. Koyanagi T, Katoh Y, Nozawa T, Snead L L, Kondo S, Henager C H, Huang Q. Recent progress in the development of SiC composites for nuclear fusion applications. J Nucl Mater 511: 544–555 (2018)

5. Xiao X F, Chou W S, Liu C J, Han Y C, Wang T M, Xiao W H, Zhang T Y, Liu R R. The nuclear industry urgently needs robot technology. Rob Technol Appl 3: 4 (2011)

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