一种Zr基非晶/晶体复合型核材料的力学性能与耐腐蚀性能的研究

罗胜; 杨亮; 郭古青; 戈涛

doi:10.11889/j.0253-3219.2016.hjs.39.020501

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一种Zr基非晶/晶体复合型核材料的力学性能与耐腐蚀性能的研究

更新时间：2021-05-24

- 一种Zr基非晶/晶体复合型核材料的力学性能与耐腐蚀性能的研究
- Enhanced mechanical properties and corrosion resistance of Zr-based amorphous/crystalline nuclear material
- 核技术 2016年39卷第2期文章编号：020501
- 作者机构：
  
  南京航空航天大学材料科学与技术学院南京 211106
  College of Material Science and Technology, Nanjing University of Aeronautics and Astronautics, Nanjing 211106, China
- 作者简介：
  
  罗胜,男,1990年出生,2013年毕业于南京航空航天大学,现为硕士研究生,核技术及应用专业
  杨亮,E-mail:yangliang@nuaa.edu.cn
- 基金信息：
- DOI：10.11889/j.0253-3219.2016.hjs.39.020501
  中图分类号： TL341
- 收稿日期：2015-11-16，
  
  录用日期：2015-12-28，
  
  纸质出版日期：2016-01-25
- 稿件说明：
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罗胜, 杨亮, 郭古青, 等. 一种Zr基非晶/晶体复合型核材料的力学性能与耐腐蚀性能的研究[J]. 核技术, 2016,39(2):020501

Sheng LUO, Liang YANG, Guqing GUO, et al. Enhanced mechanical properties and corrosion resistance of Zr-based amorphous/crystalline nuclear material[J]. Nuclear techniques, 2016, 39(2): 020501
罗胜, 杨亮, 郭古青, 等. 一种Zr基非晶/晶体复合型核材料的力学性能与耐腐蚀性能的研究[J]. 核技术, 2016,39(2):020501 DOI： 10.11889/j.0253-3219.2016.hjs.39.020501.

Sheng LUO, Liang YANG, Guqing GUO, et al. Enhanced mechanical properties and corrosion resistance of Zr-based amorphous/crystalline nuclear material[J]. Nuclear techniques, 2016, 39(2): 020501 DOI： 10.11889/j.0253-3219.2016.hjs.39.020501.

摘要

采用Zr

和Nb双靶直流共溅射方法

通过调节Nb靶的溅射功率

制备了不同Nb含量的ZrCuNb非晶薄膜。分别使用能谱仪、X射线衍射仪、高分辨透射电子显微镜观察ZrCuNb非晶薄膜的成分与结构

最终选择具有优异非晶形成能力的Zr

成分溅射到纯Zr基片上

以制备锆基非晶复合材料。研究测试Zr

非晶复合材料的力学性能与耐腐蚀性能。结果表明:与纯Zr基片相比

复合材料在弹性阶段力学性能无明显差异;而在塑性变形阶段

由于非晶薄膜与纯Zr基片的变形与断裂机制不同

该复合材料具有更好的拉伸塑性

其表现为非晶膜厚为280 nm、640 nm和960 nm的复合材料的最大拉伸塑性形变较纯Zr基片分别提高了2.72%、5.22%、4.27%;在耐腐蚀性能方面

非晶膜厚为640 nm的复合材料与纯Zr基片相比

具有较小的自腐蚀电流密度

corr

、较正的腐蚀电位

corr

以及较大的容抗弧半径

表现出更优异的耐腐蚀能力。因此

该新型Zr基复合材料在核材料领域具有潜在的应用。

Abstract

Background:

Zr-based alloys have been widely used as nuclear materials. However

enhancement of the resistance of particl

e radiation

the mechanical properties

and the corrosion resistance in alloys are still required.

Purpose:

The aim is to develop a new Zr-based nuclear material of excellent mechanical properties and corrosion resistance.

Methods:

DC magnetron sputtering method was applied to preparing ZrCuNb ternary amorphous films precipitated upon the pure zirconium substrate. The structure of ZrCuNb films was characterized using scanning electron microscopy

energy dispersive spectroscopy

X-ray diffraction

and high-resolution transmission electron microscope. Testing on mechanical properties such as tensile experiment was performed for both the ZrCuNb films/Zr substrate (the composite material) and the corresponding Zr metal plate. Corrosion resistance was studied using potentiodynamic polarization measurements.

Results:

It is found that full amorphous structure in films could be obtained microalloying Nb in ZrCu alloy

such as Zr

. In comparison with the Zr metal plate

the Zr substrate coated with Zr

film does not have higher hardness or Young's modulus

however

the composite material possesses relatively high tensile strength and in particular obviously larger plastic-strain range. The enhancement is caused by the difference in initiation mechanism of cracks between the amorphous film and Zr substrate that they propagate along different orientations. Cracks in the substrate and film interfere with each other

leading to a delayed catastrophic rupture. In addition

the composite material has a stronger corrosion resistance.

Conclusion:

Zr metal plate coated with ZrCuNb amorphous film is a novel composite material with excellent mechanical properties and good corrosion resistance

which has a potential application in the nuclear engineering.

关键词

Keywords

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