Effects of Zn injection on the oxide film characteristics of zirconium alloy fuel cladding exposed to high-temperature pressurized water with or without subcooled nucleate boiling

doi:10.1016/j.jnucmat.2024.155210

IMR OpenIR

	Effects of Zn injection on the oxide film characteristics of zirconium alloy fuel cladding exposed to high-temperature pressurized water with or without subcooled nucleate boiling
	Xue, Chaochao 1,2,4; Liu, Xiaohan 3; Chen, Zhongcun 3; Zhang, Ziyu 1; Wu, Xinqiang 1; Tan, Jibo 1; Han, En-Hou 1,4
通讯作者	Zhang, Ziyu(zyzhang14b@imr.ac.cn)
	2024-10-01
发表期刊	JOURNAL OF NUCLEAR MATERIALS
ISSN	0022-3115
卷号	599 页码:14
摘要	The effects of Zn injection on the oxide film characteristics of zirconium alloy fuel cladding were investigated following corrosion tests in borated and lithiated high-temperature pressurized water, with and without subcooled nucleate boiling (SNB). In the absence of SNB, the thickness, elemental distribution and crystallographic detail of the oxide film, weight gain of the cladding specimen were examined. No obvious differences caused by Zn injection were found. In SNB condition, corrosion nodules were found on cladding surface and the crud tended to deposit on these corrosion nodules. However, Zn injection did not obviously affect the density and characteristic of the corrosion nodules. The mechanism of crud deposition on corrosion nodules was discussed. Regardless of SNB implementation, no discernible Zn enrichments in the zirconium oxide, second-phase particles and oxide-metal interface region were found. Thermodynamic analyses further affirmed that Zn cannot be incorporated into the zirconium alloy oxide spontaneously.
关键词	Zirconium alloy cladding Zn injection Oxide film characteristics Crud deposition Thermodynamic analyses
资助者	National Natural Science Foundation of China ; IMR Innovation Fund
DOI	10.1016/j.jnucmat.2024.155210
收录类别	SCI
语种	英语
资助项目	National Natural Science Foundation of China[52171085] ; IMR Innovation Fund[2023- PY09]
WOS研究方向	Materials Science ; Nuclear Science & Technology
WOS类目	Materials Science, Multidisciplinary ; Nuclear Science & Technology
WOS记录号	WOS:001253461800001
出版者	ELSEVIER
引用统计
文献类型	期刊论文
条目标识符	http://ir.imr.ac.cn/handle/321006/187451
专题	中国科学院金属研究所
通讯作者	Zhang, Ziyu
作者单位	1.Chinese Acad Sci, Inst Met Res, CAS Key Lab Nucl Mat & Safety Assessment, Liaoning Key Lab Safety & Assessment Tech Nucl Mat, Shenyang 110016, Peoples R China 2.Univ Sci & Technol China, Sch Mat Sci & Engn, Shenyang 110016, Peoples R China 3.China Nucl Power Technol Res Inst, Shenzhen 518000, Peoples R China 4.South China Univ Technol, Guangzhou Int Campus, Guangzhou 511442, Peoples R China
推荐引用方式 GB/T 7714	Xue, Chaochao,Liu, Xiaohan,Chen, Zhongcun,et al. Effects of Zn injection on the oxide film characteristics of zirconium alloy fuel cladding exposed to high-temperature pressurized water with or without subcooled nucleate boiling[J]. JOURNAL OF NUCLEAR MATERIALS,2024,599:14.
APA	Xue, Chaochao.,Liu, Xiaohan.,Chen, Zhongcun.,Zhang, Ziyu.,Wu, Xinqiang.,...&Han, En-Hou.(2024).Effects of Zn injection on the oxide film characteristics of zirconium alloy fuel cladding exposed to high-temperature pressurized water with or without subcooled nucleate boiling.JOURNAL OF NUCLEAR MATERIALS,599,14.
MLA	Xue, Chaochao,et al."Effects of Zn injection on the oxide film characteristics of zirconium alloy fuel cladding exposed to high-temperature pressurized water with or without subcooled nucleate boiling".JOURNAL OF NUCLEAR MATERIALS 599(2024):14.