Experimental Investigation for the Fretting Wear of Cr-coated Zircaloy Cladding

Yang Siyuan; Yuan Bo; Wen Qinglong; Wen Shuang; Zhang Ruiqian; Yang Hongyan

doi:10.13832/j.jnpe.2024.S1.0103

Volume 45 Issue S1

Jun. 2024

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Yang Siyuan, Yuan Bo, Wen Qinglong, Wen Shuang, Zhang Ruiqian, Yang Hongyan. Experimental Investigation for the Fretting Wear of Cr-coated Zircaloy Cladding[J]. Nuclear Power Engineering, 2024, 45(S1): 103-109. doi: 10.13832/j.jnpe.2024.S1.0103

Citation:

Yang Siyuan, Yuan Bo, Wen Qinglong, Wen Shuang, Zhang Ruiqian, Yang Hongyan. Experimental Investigation for the Fretting Wear of Cr-coated Zircaloy Cladding[J]. Nuclear Power Engineering, 2024, 45(S1): 103-109. doi: 10.13832/j.jnpe.2024.S1.0103

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Experimental Investigation for the Fretting Wear of Cr-coated Zircaloy Cladding

doi: 10.13832/j.jnpe.2024.S1.0103

Yang Siyuan^{1, 2, 3
,},
Yuan Bo^{1, 2, 3
,
,},
Wen Qinglong^{1, 2, 3},
Wen Shuang^{1, 2, 3},
Zhang Ruiqian⁴,
Yang Hongyan⁴

1.
School of Energy and Power Engineering, Chongqing University, Chongqing, 400044, China
2.
Key Laboratory of Low-grade Energy Utilization Technologies and Systems, Ministry of Education, Chongqing University, Chongqing, 400044, China
3.
Liangjiang Laboratory for New Energy (Nuclear Energy and Power), Chongqing, 400044, China
4.
Nuclear Power Institute of China, Chengdu, 610213, China

Received Date: 2023-12-28
Rev Recd Date: 2024-04-09
Publish Date: 2024-06-15

Abstract

Abstract

To study the mechanism and microscopic mechanism of fretting wear of Cr-coated zircaloy cladding under the condition of turbulent excitation of PWR, this paper mainly takes Cr-coated zircaloy cladding as the research object, carries out experimental research on fretting wear under multi-parameter coupling, and expounds the influence laws of parameters such as frequency, load, displacement and cycle times on fretting wear. The maximum wear depth and wear volume of 19 sets of fretting wear experiments were obtained, of which the maximum wear depth was 12.052 µm and the maximum wear volume was 3.301×10⁻³ mm³. The results show that the main influencing parameters of fretting wear include fretting amplitude, normal load, cycle times and material hardness, while fretting frequency has little influence on wear volume and maximum wear depth. The least square method is used to fit the experimental results to obtain the wear volume calculation formula, and the deviation between the experimental value and the calculated value of the formula is within ±50%. This study provides data support for the evaluation of wear resistance of Cr-coated zircaloy cladding.
- Cr-coated zircaloy cladding,
- Fretting wear,
- Experimental research

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References(10)

References

[1]	TERRANI K A. Accident tolerant fuel cladding development: promise, status, and challenges[J]. Journal of Nuclear Materials, 2018, 501: 13-30. doi: 10.1016/j.jnucmat.2017.12.043
[2]	International Atomic Energy Agency. Review of fuel failures in water cooled reactors (2006-2015)[M]. Vienna: International Atomic Energy Agency, 2010: 9.
[3]	KIM H K, KIM S J, YOON K H, et al. Fretting wear of laterally supported tube[J]. Wear, 2001, 250(1-12): 535-543. doi: 10.1016/S0043-1648(01)00634-2
[4]	KIM T H, KIM S S. Fretting wear mechanisms of zircaloy-4 and Inconel 600 contact in air[J]. KSME International Journal, 2001, 15(9): 1274-1280. doi: 10.1007/BF03185668
[5]	FISHER N J, WECKWERTH M K, GRANDISON D A E, et al. Fretting-wear of zirconium alloys[J]. Nuclear Engineering and Design, 2002, 213(1): 79-90. doi: 10.1016/S0029-5493(02)00035-3
[6]	JOULIN T P, GUÉROUT F M, LINA A, et al. Effects of loading conditions and types of motion on PWR fuel rod cladding wear[C]//5th International Symposium on Fluid Structure Interaction, Aeroelasticity, and Flow Induced Vibration and Noise. New Orleans: ASME, 2002: 1011-1018.
[7]	LEE Y H, BYUN T S. A comparative study on the wear behaviors of cladding candidates for accident-tolerant fuel[J]. Journal of Nuclear Materials, 2015, 465: 857-865. doi: 10.1016/j.jnucmat.2015.05.017
[8]	ARCHARD J F. Contact and rubbing of flat surfaces[J]. Journal of Applied Physics, 1953, 24(8): 981-988. doi: 10.1063/1.1721448
[9]	BLAU P J. A multi-stage wear model for grid-to-rod fretting of nuclear fuel rods[J]. Wear, 2014, 313(1-2): 89-96. doi: 10.1016/j.wear.2014.02.016
[10]	BLAU P J. A microstructure-based wear model for grid-to-rod fretting of clad nuclear fuel rods[J]. Wear, 2019, 426-427: 750-759. doi: 10.1016/j.wear.2019.01.056