Corrosion behavior of high-level waste container materials Ti and Ti–Pd alloy under long-term gamma irradiation in Beishan groundwater

IOCAS-IR

	Corrosion behavior of high-level waste container materials Ti and Ti–Pd alloy under long-term gamma irradiation in Beishan groundwater
	魏强林 ; 李玉红 ; 黄彦良 ; 杨冬燕 ; 杨波 ; 刘义保
发表期刊	Chinese Physics B
ISSN	1674-1056
	2021-05-15
出版年	2021
卷号	v.30 期号:05 页码:483-490
文献类型	CNKI期刊论文
摘要	Titanium and titanium–palladium alloys are important potential materials for nuclear waste container, which will endure both intense γ-irradiation and groundwater erosion. Therefore, it is very important to investigate the corrosion behavior of the container materials. In this research, the cumulative dose effect of TA8-1 type titanium–palladium alloy(TA8-1) and TA2-type pure titanium(TA2) under γ-irradiation was studied based on the geological disposal of nuclear wastes. The irradiation experiments were performed at room temperature using60 Co gamma sources with a 5.0-k Gy·h-1 intensity for 40, 80 or 160 days, respectively. The p H value and conductivity of Beishan groundwater were investigated.The results showed that the p H value changed from alkaline(8.22) to acidic(2.46 for TA8-1 and 2.44 for TA2), while the un-irradiated solution remained alkaline(8.17 for TA8-1 and 8.20 for TA2) after 160 days. With the increase of irradiation dose, the conductivity increases rapidly and then tends to become stable, which indicates that the titanium dioxide corrosion layer formed on the surface of the sample surface effectively prevents further corrosion. Meanwhile, XRD and SEM–EDS analysis results show that the main components of corrosion products are Ti O_2 and Ti O. The titanium on the surface of the sample is oxidized, resulting in slight uneven local corrosion. The results show that TA8-1 and TA2 are suitable to be used as candidate materials for high-level waste(HLW) disposal containers due to their excellent performance under long-term and high-dose irradiation corrosion.
关键词	γ-irradiation corrosion high-level waste container material
CNKI专辑号	A;B;C;
CNKI专辑名称	基础科学;工程科技Ⅰ辑;工程科技Ⅱ辑;
CNKI专题号	B022;C040;
CNKI专题名称	金属学及金属工艺;核科学技术;
分类号	TG174.3;TL942
收录类别	中科院核心 ; 中科院扩展
语种	英文;
资助项目(基金）	Project supported by the National Natural Science Foundation of China (Grant Nos. 51471160, 11775102, and 11965001) ; the Fundamental Research Funds for the Central Universities,China (Lanzhou University, Grant No. lzujbky-2018-19)
文献类型	CNKI期刊论文
条目标识符	http://ir.qdio.ac.cn/handle/337002/187773
专题	中国科学院海洋研究所
作者单位	1.SchoolofNuclearScienceandTechnology,LanzhouUniversity 2.StateKeyLaboratoryofNuclearResourcesandEnvironment,EastChinaUniversityofTechnology 3.InstituteofOceanology,ChineseAcademyofSciences
推荐引用方式 GB/T 7714	魏强林,李玉红,黄彦良,等. Corrosion behavior of high-level waste container materials Ti and Ti–Pd alloy under long-term gamma irradiation in Beishan groundwater. 2021.