Fretting wear behavior of zirconium alloy in B-Li water at 300 °C

被引：34

作者：

Zhang, Lefu ^{[1
]}

Lai, Ping ^{[1
]}

Liu, Qingdong ^{[1
]}

Zeng, Qifeng ^{[2
]}

Lu, Junqiang ^{[2
]}

Guo, Xianglong ^{[1
]}

机构：

[1] Shanghai Jiao Tong Univ, Sch Nucl Sci & Engn, 800 Dongchuan Rd, Shanghai 200240, Peoples R China

[2] Shanghai Nucl Engn Res & Design Inst, 29 Hongcao Rd, Shanghai 200233, Peoples R China

来源：

JOURNAL OF NUCLEAR MATERIALS | 2018年 / 499卷

关键词：

Fretting wear; Zirconium alloy; B-Li water; Wear mode; Oxide layer; HIGH-TEMPERATURE WATER; INCONEL; 690; ALLOY; SURFACE-ROUGHNESS; CONTACT; STEEL; HARDNESS; DEBRIS; FUEL; METHODOLOGY; MECHANISMS;

D O I：

10.1016/j.jnucmat.2017.12.003

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

The tangential fretting wear of three kinds of zirconium alloys tube mated with 304 stainless steel (SS) plate was investigated. The tests were conducted in an autoclave containing 300 degrees C pressurized B-Li water for tube-on-plate contact configuration. The worn surfaces were examined with scanning electron microscopy (SEM), energy dispersive spectroscopy (EDS) and 3D microscopy. The cross-section of wear scar was examined with transmission electron microscope (TEM). The results indicated that the dominant wear mechanism of zirconium alloys in this test condition was delamination and oxidation. The oxide layer on the fretted area consists of outer oxide layer composed of iron oxide and zirconium oxide and inner oxide layer composed of zirconium oxide. (C) 2017 Published by Elsevier B.V.

引用

页码：401 / 409

页数：9

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