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材料研究学报  2026, Vol. 40 Issue (3): 217-224    DOI: 10.11901/1005.3093.2025.204
  研究论文 本期目录 | 过刊浏览 |
模拟重水堆一回路水中Zr-2.5Nb压力管与承重垫片的微动磨损行为
赵冠楠1, 王术极2,3, 张玉圣2(), 明洪亮2(), 习建勋4, 王俭秋2, 韩恩厚5
1.上海核工程研究设计院股份有限公司 核电关键材料全国重点实验室 上海 200233
2.中国科学院金属研究所 中国科学院核用材料与安全评价重点实验室 沈阳 110016
3.东北大学材料科学与工程学院 沈阳 110819
4.中核北方核燃料元件有限公司 包头 014035
5.广东省腐蚀科学与技术创新研究院 广州 510530
Fretting Wear Behavior of Zr-2.5Nb Pressure Tubes Coupled with Bearing Pads in a Simulated Water of Primary Loop for Heavy Water Reactor
ZHAO Guannan1, WANG Shuji2,3, ZHANG Yusheng2(), MING Hongliang2(), XI Jianxun4, WANG Jianqiu2, HAN En-Hou5
1.State Key Laboratory of Materials for Advanced Nuclear Energy, Shanghai Nuclear Engineering Research & Design Institute Co., Ltd., Shanghai 200233, China
2.CAS Key Laboratory of Nuclear Materials and Safety Assessment, Institute of Metal Research, Chinese Academy of Sciences, Shenyang 110016, China
3.School of Materials Science and Engineering, Northeastern University, Shenyang 110819, China
4.China North Nuclear Fuel Co., Ltd., Baotou 014035, China
5.Institute of Corrosion Science and Technology, Guangzhou 510530, China
引用本文:

赵冠楠, 王术极, 张玉圣, 明洪亮, 习建勋, 王俭秋, 韩恩厚. 模拟重水堆一回路水中Zr-2.5Nb压力管与承重垫片的微动磨损行为[J]. 材料研究学报, 2026, 40(3): 217-224.
Guannan ZHAO, Shuji WANG, Yusheng ZHANG, Hongliang MING, Jianxun XI, Jianqiu WANG, En-Hou HAN. Fretting Wear Behavior of Zr-2.5Nb Pressure Tubes Coupled with Bearing Pads in a Simulated Water of Primary Loop for Heavy Water Reactor[J]. Chinese Journal of Materials Research, 2026, 40(3): 217-224.

全文: PDF(11808 KB)   HTML
摘要: 

研究了模拟重水堆一回路水中两种典型振动工况下Zr-2.5Nb压力管与承重垫片间的微动磨损行为,并分析了压力管的损伤程度、磨损机制和材料的退化方式。结果表明:压力管的主要磨损机制为磨粒磨损,亚机制为微耕;在严苛振动工况下压力管的磨粒磨损加剧,使压力管严重损伤。还详细讨论了磨粒和犁沟槽的形成机制。

关键词 : 材料失效与保护,  微动磨损,  压力管,  高温高压水    
Abstract:

Fretting wear between Zr-2.5Nb pressure tubes and bearing pads occurs inevitably owing to flow induced vibration during the operation of heavy water reactor, which can be regarded as one of the main failure forms of pressure tubes. The fretting wear behavior between Zr-2.5Nb pressure tubes and bearing pads under two typical vibration conditions in a simulated water of primary loop for heavy water reactor was investigated. The wear degree, wear mechanism and material degradation form of the pressure tube were analyzed. The results showed that the main wear mechanism of the pressure tube was abrasive wear, and the sub-mechanism was micro-ploughing. Abrasive wear of the pressure tube was aggravated under severe vibration condition, resulting in a serious damage of the pressure tube. In addition, the formation mechanisms of abrasives and grooves were discussed in detail.

Key words: materials failure and protection    fretting wear    pressure tube    high temperature pressurized water
收稿日期: 2025-06-13     
ZTFLH:  TB31  
基金资助:国家资助博士后研究人员计划(C档)(GZC20232749);中国科学院金属研究所创新基金(2024-PY13);中国科学院青年创新促进会(2022187)
通讯作者: 张玉圣,助理研究员,yshzhang19b@imr.ac.cn,研究方向为核用材料微动磨损;
明洪亮,研究员,hlming12s@imr.ac.cn,研究方向为核用材料损伤评价
Corresponding author: ZHANG Yusheng, Tel: (024)23998826, E-mail: yshzhang19b@imr.ac.cn;
MING Hongliang, Tel: (024)23998826, E-mail: hlming12s@imr.ac.cn
作者简介: 赵冠楠,男,1987年生,博士,高级工程师
图1  压力管和垫片试样的实物图
图2  两种工况下Ft-D曲线随微动周次的变化
图3  两种工况下Zr-2.5Nb压力管内壁磨损区3D形貌
图4  两种工况下Zr-2.5Nb压力管内壁的磨损区轮廓
图5  两种工况下Zr-2.5Nb压力管内壁磨损区SEM表面形貌
图6  在10 N下Zr-2.5Nb压力管内壁磨损区截面SEM形貌
图7  在40 N下Zr-2.5Nb压力管内壁磨损区截面SEM形貌
[1] Fang J T, Peng J F, Tang P, et al. Effect of temperature on fretting wear behaviors of Zr-4 zirconium alloy under different operating conditions [J]. Mater. Mech. Eng., 2023, 47(1): 56
[1] 方婧婷, 彭金方, 唐 攀 等. 温度对不同运行工况下Zr-4锆合金微动磨损行为的影响 [J]. 机械工程材料, 2023, 47(1): 56
doi: 10.11973/jxgccl202301008
[2] Lazarevic S, Lu R Y, Favede C, et al. Investigating grid-to-rod fretting wear of nuclear fuel claddings using a unique autoclave fretting rig [J]. Wear, 2018, 412-413: 30
doi: 10.1016/j.wear.2018.06.011
[3] Kim T H, Kim S S. Fretting wear mechanisms of Zircaloy-4 and Inconel 600 contact in air [J]. KSME Int. J., 2001, 15(9): 1274
doi: 10.1007/BF03185668
[4] Kim H K, Lee Y H. Influence of contact shape and supporting condition on tube fretting wear [J]. Wear, 2003, 255(7-12): 1183
doi: 10.1016/S0043-1648(03)00068-1
[5] Lee Y H, Kim H K. Effect of spring shapes on the variation of loading conditions and the wear behaviour of the nuclear fuel rod during fretting wear tests [J]. Wear, 2007, 263(1-6): 451
doi: 10.1016/j.wear.2006.12.071
[6] Zhang Y S, Lai J, Ming H L, et al. Effect of normal force on fretting wear behavior of zirconium alloy tube in simulated primary water of PWR [J]. Acta Metall. Sin. -Engl. Lett., 2023, 36(5): 865
[7] Zhuang W H, Lai P, Lu H, et al. The transformation of fretting corrosion mechanism of zirconium alloy tube mating with 304 stainless steel in high temperature high pressure water [J]. J. Nucl. Mater., 2023, 577: 154304
doi: 10.1016/j.jnucmat.2023.154304
[8] Li Z Y, Cai Z B, Zhang W, et al. Effect of coolant pH on the fretting corrosion behavior of zirconium alloy [J]. Wear, 2022, 496-497: 204269
doi: 10.1016/j.wear.2022.204269
[9] Jiang H X, Duan Z W, Zhang B B, et al. Wear behavior of zirconium-4 alloy after different irradiation damage level [J]. Appl. Surf. Sci., 2020, 509: 145373
doi: 10.1016/j.apsusc.2020.145373
[10] Jiang H X, Duan Z W, Zhang B B, et al. Fretting wear behaviors of Zr-4 alloy under different ions irradiation conditions [J]. Tribol. Int., 2020, 152: 106553
doi: 10.1016/j.triboint.2020.106553
[11] Zhang Y S, Lai J, Wang J Z, et al. Establishment of fretting maps of Zr alloy cladding tube mated with Zr alloy dimple in simulated primary water of pressurized water reactor [J]. Tribol. Int., 2023, 178: 108065
doi: 10.1016/j.triboint.2022.108065
[12] Zhang Y S, Ming H L, Lai J, et al. Fretting wear behaviour of Zr alloy cladding tube under partial slip regime with different duration in simulated primary water of PWR [J]. Appl. Surf. Sci., 2022, 605: 154861
doi: 10.1016/j.apsusc.2022.154861
[13] Zhang Y S, Ming H L, Lai J, et al. Fretting wear behavior of Zr alloy cladding tube mated with Zr alloy dimple under mixed fretting regime in simulated primary water of PWR [J]. J. Mater. Sci. Technol., 2023, 158: 43
doi: 10.1016/j.jmst.2023.02.037
[14] Zhang Y S, Ming H L, Wang S J, et al. Evolution of fretting wear behavior of zirconium alloy cladding tube under gross slip regime in simulated primary water of pressurized water reactor [J]. J. Mater. Sci. Technol., 2025, 220: 276
doi: 10.1016/j.jmst.2024.09.022
[15] Zhang Y S, Wu B, Ming H L, et al. Effects of displacement amplitude and normal force on fretting wear behavior of zirconium alloy tube in simulated primary water of PWR [J]. Wear, 2024, 542-543: 205271
doi: 10.1016/j.wear.2024.205271
[16] Fisher N J, Weckwerth M K, Grandison D A E, et al. Fretting-wear of zirconium alloys [A]. Transactions of the 14th International Conference on Structural Mechanics in Reactor Technology [C]. Lyon, 1997: 183
[17] Hamilton R C, Stern F. A Summary of Recent Zircaloy Fretting Wear Tests at Westinghouse Canada Limited [M]. Pinawa: Whiteshell Nuclear Research Establishment, 1980
[18] Schmugar K L. Vibration Wear of Fuel Rods [M]. ASME, 1979
[19] Alicino F, Zampini G. Integrity Assessment of Zircaloy-2 Pressure Tube with Fretting Corrosion Defects [M]. Conf. on Pressure Vessel Tech., 1984
[20] Attia M H. Fretting wear of Zr-alloy pressure tubes under the combined effects of in-plane and out-of-plane flow-induced vibrations [J]. Wear, 2005, 259(1-6): 319
doi: 10.1016/j.wear.2005.01.028
[21] Fisher N J, Weckwerth M K, Grandison D A E, et al. Fretting-wear of zirconium alloys [J]. Nucl. Eng. Des., 2002, 213(1): 79
doi: 10.1016/S0029-5493(02)00035-3
[22] Attia M H, de Pannemaecker A, Williams G. Effect of temperature on tribo-oxide formation and the fretting wear and friction behavior of zirconium and nickel-based alloys [J]. Wear, 2021, 476: 203722
doi: 10.1016/j.wear.2021.203722
[23] Kumar B, Kumar D, Chaudhry V. Tribological and corrosion behavior of hydrided zirconium alloy [J]. Tribol. Int., 2024, 195: 109660
doi: 10.1016/j.triboint.2024.109660
[24] Liao J J, Yang Z B, Qiu S Y, et al. The correlation between tetragonal phase and the undulated metal/oxide interface in the oxide films of zirconium alloys [J]. J. Nucl. Mater., 2019, 524: 101
doi: 10.1016/j.jnucmat.2019.06.039
[25] Liu J L, Yu H B, Karamched P, et al. Mechanism of the α-Zr to hexagonal-ZrO transformation and its impact on the corrosion performance of nuclear Zr alloys [J]. Acta Mater., 2019, 179: 328
doi: 10.1016/j.actamat.2019.08.051
[26] Zhang Y, You L, Li X W, et al. In-situ investigation of the fatigue crack initiation and propagation behavior of Zircaloy-4 with different hydrogen contents at RT and 300 oC [J]. J. Nucl. Mater., 2020, 532: 152065
doi: 10.1016/j.jnucmat.2020.152065
[27] Kim H K, Kim S J, Yoon K H, et al. Fretting wear of laterally supported tube [J]. Wear, 2001, 250(1-12): 535
doi: 10.1016/S0043-1648(01)00634-2
[28] Vingsbo O, Söderberg S. On fretting maps [J]. Wear, 1988, 126(2): 131
doi: 10.1016/0043-1648(88)90134-2
[29] Zhang Y S, Wang S J, Ming H L, et al. Study of fretting wear behavior of 690TT heat exchanger tube under three fretting regimes in high temperature pressurized water [J]. J. Nucl. Mater., 2025, 605: 155559
doi: 10.1016/j.jnucmat.2024.155559
[30] Archard J F. Contact and rubbing of flat surfaces [J]. J. Appl. Phys., 1953, 24(8): 981
doi: 10.1063/1.1721448
[31] Zhang Y S, Ming H L, Tang L C, et al. Effect of the frequency on fretting corrosion behavior between Alloy 690TT tube and 405 stainless steel plate in high temperature pressurized water [J]. Tribol. Int., 2021, 164: 107229
doi: 10.1016/j.triboint.2021.107229
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