Predicting Radionuclide Release Rates from Spent Nuclear Fuel Inside a Failed Waste Disposal Container Using a Finite Element Model

doi:10.5006/2866

	Predicting Radionuclide Release Rates from Spent Nuclear Fuel Inside a Failed Waste Disposal Container Using a Finite Element Model
	Liu, Nazhen 1,2; Zhu, Ziyan 1; Wu, Linda 3; Qin, Zack 1; Noel, James J.1,4; Shoesmith, David W.1,4
	2019-03-01
发表期刊	CORROSION
ISSN	0010-9312
卷号	75 期号:3 页码:302-308
通讯作者	Liu, Nazhen(nliu63@uwo.ca)
摘要	Models for the corrosion of spent nuclear fuel (fission and actinide-doped uranium dioxide) provide the essential source term for the release of radionuclides from within a failed nuclear waste container in a deep geologic repository. Although redox conditions within a repository are expected to be anoxic, exposure of the fuel to groundwater will cause the generation of oxidants at the fuel surface, leading to its corrosion and the release of radionuclides. The influence of these oxidants will be partially mitigated by the anoxic corrosion of the inner walls of the steel container to produce the oxidant scavengers, Fe2+ and H-2. This review summarizes the development of a finite element model developed to determine the influence of the various redox-controlling species (H2O2, Fe2+, H-2). Both one-dimensional and two-dimensional models are described, with the latter required to take into account the fractured geometry of the fuel.
关键词	COMSOL corrosion modeling spent nuclear fuel uranium dioxide waste disposal
DOI	10.5006/2866
收录类别	SCI
语种	英语
WOS研究方向	Materials Science ; Metallurgy & Metallurgical Engineering
WOS类目	Materials Science, Multidisciplinary ; Metallurgy & Metallurgical Engineering
WOS记录号	WOS:000459019700008
出版者	NATL ASSOC CORROSION ENG
引用统计	被引频次：4[WOS] [WOS记录] [WOS相关记录]
文献类型	期刊论文
条目标识符	http://ir.qdio.ac.cn/handle/337002/155403
专题	海洋环境腐蚀与生物污损重点实验室
通讯作者	Liu, Nazhen
作者单位	1.Univ Western Ontario, Dept Chem, London, ON N6A 5B7, Canada 2.Chinese Acad Sci, Inst Oceanol, Key Lab Marine Environm Corros & Biofouling, Qingdao 266071, Peoples R China 3.Canadian Nucl Labs, Chalk River, ON K0J 1J0, Canada 4.Univ Western Ontario, Surface Sci Western, London, ON N6G 0J3, Canada
第一作者单位	中国科学院海洋研究所
通讯作者单位	中国科学院海洋研究所
推荐引用方式 GB/T 7714	Liu, Nazhen,Zhu, Ziyan,Wu, Linda,et al. Predicting Radionuclide Release Rates from Spent Nuclear Fuel Inside a Failed Waste Disposal Container Using a Finite Element Model[J]. CORROSION,2019,75(3):302-308.
APA	Liu, Nazhen,Zhu, Ziyan,Wu, Linda,Qin, Zack,Noel, James J.,&Shoesmith, David W..(2019).Predicting Radionuclide Release Rates from Spent Nuclear Fuel Inside a Failed Waste Disposal Container Using a Finite Element Model.CORROSION,75(3),302-308.
MLA	Liu, Nazhen,et al."Predicting Radionuclide Release Rates from Spent Nuclear Fuel Inside a Failed Waste Disposal Container Using a Finite Element Model".CORROSION 75.3(2019):302-308.

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