Fretting corrosion behavior and microstructure evolution of hydrided zirconium alloy under gross slip regime in high temperature high pressure water environment

被引:1
作者
Kang, L. Z. [1 ]
Lu, Y. H. [1 ]
Bian, W. W. [1 ]
Yu, P. J. [1 ]
Wang, Y. . B. [1 ]
Xin, L. [1 ]
Han, Y. M. [1 ]
机构
[1] Univ Sci & Technol Beijing, Natl Ctr Mat Serv Safety, Beijing 100083, Peoples R China
基金
中国国家自然科学基金;
关键词
Fretting corrosion; Zirconium alloy; Hydrogen; High temperature high pressure water; MECHANICAL-PROPERTIES; DISSOLVED HYDROGEN; WEAR-RESISTANCE; ZIRCALOY-4; PRECIPITATION; 1ST-PRINCIPLES; ABSORPTION; OXIDATION; FRICTION;
D O I
10.1016/j.corsci.2024.112582
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Fretting corrosion of hydrided Zr-alloy under gross slip regime in high temperature high pressure water were investigated. The results indicated that hydrogen charging decreased wear volume significantly. At low hydrogen content, tetragonal ZrO2 was formed at the oxide/tribologically transformed structure (TTS) interface, which induced cracks and delamination. From worn surface to matrix there were third body layer (TBL), TTS and deformation layer. At high hydrogen content, an oxide layer consisting mainly of monoclinic ZrO2 was formed, from worn surface to matrix there were TBL, oxide layer, TTS and deformation layer, and the main damage mechanisms were oxidation and adhesive wear.
引用
收藏
页数:12
相关论文
共 51 条
[1]   The effects of ultrasonic nanocrystal surface modification temperature on the mechanical properties and fretting wear resistance of Inconel 690 alloy [J].
Amanov, A. ;
Umarov, R. .
APPLIED SURFACE SCIENCE, 2018, 441 :515-529
[2]   Effect of temperature on tribo-oxide formation and the fretting wear and friction behavior of zirconium and nickel-based alloys [J].
Attia, M. Helmi ;
de Pannemaecker, Alix ;
Williams, Gary .
WEAR, 2021, 476
[3]   A review on hydride precipitation in zirconium alloys [J].
Bair, Jacob ;
Zaeem, Mohsen Asle ;
Tonks, Michael .
JOURNAL OF NUCLEAR MATERIALS, 2015, 466 :12-20
[4]   Sequence and mechanism of early microstructure evolution in alloy 690TT subjected to fretting corrosion in high temperature pressurized water [J].
Bian, W. W. ;
Lu, Y. H. ;
Kang, L. Z. ;
Han, Y. M. ;
Xin, L. ;
Liu, X. ;
Shoji, T. .
CORROSION SCIENCE, 2023, 221
[5]  
Blat M., 1996, ZIRCONIUM NUCL IND 1, V1295, P319
[6]   PRECIPITATION OF ZIRCONIUM HYDRIDE IN ZIRCONIUM AND ZIRCALOY-2 [J].
BRADBROOK, JS ;
RIDLEY, N ;
LORIMER, GW .
JOURNAL OF NUCLEAR MATERIALS, 1972, 42 (02) :142-+
[7]   A review of fretting study on nuclear power equipment [J].
Cai, Zhen-bing ;
Li, Zheng-yang ;
Yin, Mei-gui ;
Zhu, Min-hao ;
Zhou, Zhong-rong .
TRIBOLOGY INTERNATIONAL, 2020, 144
[8]   Kinetics of hydrogen absorption in Zr-based alloys [J].
Cekic, Bozidar ;
Ciric, Katarina ;
Iordoc, Mihail ;
Markovic, Smilja ;
Mitric, Miodrag ;
Stojic, Dragica .
JOURNAL OF ALLOYS AND COMPOUNDS, 2013, 559 :162-166
[9]   Hydrogen influence on mechanical and fracture mechanics characteristics of zirconium Zr-2.5Nb alloy at ambient and elevated temperatures [J].
Daunys, Mykolas ;
Dundulis, Romualdas ;
Grybenas, Albertas ;
Krasauskas, Povilas .
NUCLEAR ENGINEERING AND DESIGN, 2008, 238 (10) :2536-2545
[10]   The role of hydrogen in zirconium alloy corrosion [J].
Ensor, B. ;
Lucente, A. M. ;
Frederick, M. J. ;
Sutliff, J. ;
Motta, A. T. .
JOURNAL OF NUCLEAR MATERIALS, 2017, 496 :301-312