Effects of coolant pH on crud deposition behavior on fuel cladding tube under subcooled nucleate boiling condition in high temperature pressurized water

doi:10.1016/j.jnucmat.2024.155454

IMR OpenIR

	Effects of coolant pH on crud deposition behavior on fuel cladding tube under subcooled nucleate boiling condition in high temperature pressurized water
	Lin, Zihao 1,2; Zhang, Ziyu 2; Tan, Jibo 2; Wu, Xinqiang 2
通讯作者	Zhang, Ziyu(zyzhang14b@imr.ac.cn)
	2025
发表期刊	JOURNAL OF NUCLEAR MATERIALS
ISSN	0022-3115
卷号	603 页码:13
摘要	The effects of coolant pH on the crud deposition behavior on the Zr alloy and the FeCrAl fuel cladding tubes under subcooled nucleate boiling condition were investigated. With the increase of coolant pH, the coverage rate and thickness of crud on the surfaces of both the Zr alloy and the FeCrAl fuel cladding tubes showed a decreasing trend. The solubility of crud compositions was reduced due to the increase of coolant pH, which resulted in the inhibition of the crud deposition process caused by SNB condition. Consequently, the elevated coolant pH value reduced the amount of crud on the surface of the fuel cladding tube.
关键词	Crud deposition Fuel cladding tube Coolant pH Subcooled nucleate boiling Solubility
资助者	National Natural Science Foundation of China ; IMR Innovation Fund ; Natural Science Foundation of Liaoning Province ; Xingliao Talent Plan of Liaoning Province ; CNNC Science Fund for Talented Young Scholars
DOI	10.1016/j.jnucmat.2024.155454
收录类别	SCI
语种	英语
资助项目	National Natural Science Foundation of China[52171085] ; National Natural Science Foundation of China[52371083] ; IMR Innovation Fund[2023-PY09] ; Natural Science Foundation of Liaoning Province[2024-MSBA-76] ; Xingliao Talent Plan of Liaoning Province[XLYC2202025] ; CNNC Science Fund for Talented Young Scholars
WOS研究方向	Materials Science ; Nuclear Science & Technology
WOS类目	Materials Science, Multidisciplinary ; Nuclear Science & Technology
WOS记录号	WOS:001335547700001
出版者	ELSEVIER
引用统计	被引频次：1[WOS] [WOS记录] [WOS相关记录]
文献类型	期刊论文
条目标识符	http://ir.imr.ac.cn/handle/321006/190675
专题	中国科学院金属研究所
通讯作者	Zhang, Ziyu
作者单位	1.Univ Sci & Technol China, Sch Mat Sci & Engn, Shenyang 110016, Peoples R China 2.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
推荐引用方式 GB/T 7714	Lin, Zihao,Zhang, Ziyu,Tan, Jibo,et al. Effects of coolant pH on crud deposition behavior on fuel cladding tube under subcooled nucleate boiling condition in high temperature pressurized water[J]. JOURNAL OF NUCLEAR MATERIALS,2025,603:13.
APA	Lin, Zihao,Zhang, Ziyu,Tan, Jibo,&Wu, Xinqiang.(2025).Effects of coolant pH on crud deposition behavior on fuel cladding tube under subcooled nucleate boiling condition in high temperature pressurized water.JOURNAL OF NUCLEAR MATERIALS,603,13.
MLA	Lin, Zihao,et al."Effects of coolant pH on crud deposition behavior on fuel cladding tube under subcooled nucleate boiling condition in high temperature pressurized water".JOURNAL OF NUCLEAR MATERIALS 603(2025):13.