Aging Behavior of B4C/6061Al Composite Materials under Irradiation Conditions
摘 要
在快中子及γ射线环境中开展了耐辐照试验,并对含26%(质量分数,下同)和31% B4C的B4C/6061Al复合材料的老化行为进行了分析。结果表明:去离子水中经受3.99×1019 nvt的快中子注量和3.30×1011 rad γ射线辐照后,试样表面颜色变深,但无明显的局部腐蚀和变形,辐照后B4C颗粒尺寸无明显变化,没有脱落现象;辐照后材料的屈服强度、抗拉强度和硬度略有增加,伸长率下降,有一定的辐照效应;辐照前后试样尺寸变化不明显,有轻微的增厚现象,说明表面形成了铝的氧化膜;辐照后材料密度略有降低,但仍然接近理论密度;辐照前后10B面密度基本没有变化。
Abstract
Irradiation test under the conditions of fast neutrons and γ ray were performed on B4C/6061Al composite materials with 26% and 31% B4C respectively, and the aging behavior of the B4C/6061Al composite materials were analyzed. The results show that the surface color of the specimens darkened after irradiation test in deionized water with fast neutrons dose 3.99×1019 nvt and γ ray dose 3.30×1011 rad, but no obvious localized corrosion and deformation occurred. The dimension of B4C particles was stable and no B4C particle was falling off from the base materials after irradiation. Yield strength, tensile strength and hardness increased slightly and the elongation decreased after irradiation, which indicated that there was certain irradiation effect. There was no obvious change on dimension of the specimen before and after irradiation, while the thickness was increased slightly, this indicated that certain aluminum oxide film was formed on the surface, the densities of the materials decreased after irradiation but they were still close to the theoretical densities. The 10B areal density was almost unchanged before and after irradiation.
中图分类号 TG174 DOI 10.11973/fsyfh-202009008
所属栏目 核电设备的腐蚀与防护
基金项目
收稿日期 2019/8/13
修改稿日期
网络出版日期
作者单位点击查看
引用该论文: ZHENG Yue,LU Keke,YUAN Wei,GAO Yang,TAI Jiang,WANG Quanzhao. Aging Behavior of B4C/6061Al Composite Materials under Irradiation Conditions[J]. Corrosion & Protection, 2020, 41(9): 45
共有人对该论文发表了看法,其中:
人认为该论文很差
人认为该论文较差
人认为该论文一般
人认为该论文较好
人认为该论文很好
参考文献
【1】KERTI I,TOPTAN F. Microstructural variations in cast B4C-reinforced aluminium matrix composites (AMCs)[J]. Materials Letters,2008,62(8/9):1215-1218.
相关信息