STEM-EDS analysis of fission products in neutron-irradiated TRISO fuel particles from AGR-1 experiment
Leng, B; van Rooyen, IJ; Wu, YQ; Szlufarska, I; Sridharan, K; van Rooyen, IJ (reprint author), Idaho Natl Lab, Fuel Design & Dev Dept, Idaho Falls, ID 83415 USA.
2016
发表期刊JOURNAL OF NUCLEAR MATERIALS
ISSN0022-3115
卷号475期号:-页码:62—70
文章类型期刊文献
摘要Historic and recent post-irradiation-examination from the German AVR and Advanced Gas Reactor Fuel Development and Qualification Project have shown that 110 m Ag is released from intact tristructural isotropic (TRISO) fuel. Although TRISO fuel particle research has been performed over the last few decades, little is known about how metallic fission products are transported through the SiC layer, and it was not until March 2013 that Ag was first identified in the SiC layer of a neutron-irradiated TRISO fuel particle. The existence of Pd-and Ag-rich grain boundary precipitates, triple junction precipitates, and Pd nano-sized intragranular precipitates in neutron-irradiated TRISO particle coatings was investigated using Scanning Transmission Electron Microscopy and Energy Dispersive Spectroscopy analysis to obtain more information on the chemical composition of the fission product precipitates. A U-rich fission product honeycomb shape precipitate network was found near a micron-sized precipitate in a SiC grain about similar to 5 mu m from the SiC-inner pyrolytic carbon interlayer, indicating a possible intragranular transport path for uranium. A single Ag-Pd nano-sized precipitate was found inside a SiC grain, and this is the first research showing such finding in irradiated SiC. This finding may possibly suggest a possible Pd-assisted intragranular transport mechanism for Ag and may be related to void or dislocation networks inside SiC grains. Preliminary semi-quantitative analysis indicated the micron-sized precipitates to be Pd2Si2U with carbon existing inside these precipitates. However, the results of such analysis for nano-sized precipitates may be influenced by the SiC matrix. The results reported in this paper confirm the co-existence of Cd with Ag in triple points reported previously. (C) 2016 Published by Elsevier B.V.
关键词Silicon-carbide Ag Diffusion Coated Particles Silver Diffusion Identification Transport Palladium Release Pd
DOI10.1016/j.jnucmat.2016.03.008
收录类别SCI
语种英语
WOS记录号WOS:000377307300008
引用统计
被引频次:2[WOS]   [WOS记录]     [WOS相关记录]
文献类型期刊论文
条目标识符http://ir.sinap.ac.cn/handle/331007/25837
专题中科院上海应用物理研究所2011-2018年
通讯作者van Rooyen, IJ (reprint author), Idaho Natl Lab, Fuel Design & Dev Dept, Idaho Falls, ID 83415 USA.
推荐引用方式
GB/T 7714
Leng, B,van Rooyen, IJ,Wu, YQ,et al. STEM-EDS analysis of fission products in neutron-irradiated TRISO fuel particles from AGR-1 experiment[J]. JOURNAL OF NUCLEAR MATERIALS,2016,475(-):62—70.
APA Leng, B,van Rooyen, IJ,Wu, YQ,Szlufarska, I,Sridharan, K,&van Rooyen, IJ .(2016).STEM-EDS analysis of fission products in neutron-irradiated TRISO fuel particles from AGR-1 experiment.JOURNAL OF NUCLEAR MATERIALS,475(-),62—70.
MLA Leng, B,et al."STEM-EDS analysis of fission products in neutron-irradiated TRISO fuel particles from AGR-1 experiment".JOURNAL OF NUCLEAR MATERIALS 475.-(2016):62—70.
条目包含的文件 下载所有文件
文件名称/大小 文献类型 版本类型 开放类型 使用许可
STEM-EDS analysis of(2412KB)期刊论文作者接受稿开放获取CC BY-NC-SA浏览 下载
个性服务
推荐该条目
保存到收藏夹
查看访问统计
导出为Endnote文件
谷歌学术
谷歌学术中相似的文章
[Leng, B]的文章
[van Rooyen, IJ]的文章
[Wu, YQ]的文章
百度学术
百度学术中相似的文章
[Leng, B]的文章
[van Rooyen, IJ]的文章
[Wu, YQ]的文章
必应学术
必应学术中相似的文章
[Leng, B]的文章
[van Rooyen, IJ]的文章
[Wu, YQ]的文章
相关权益政策
暂无数据
收藏/分享
文件名: STEM-EDS analysis of fission products in neutron-irradiated TRISO fuel particles from AGR-1 experiment.pdf
格式: Adobe PDF
所有评论 (0)
暂无评论
 

除非特别说明,本系统中所有内容都受版权保护,并保留所有权利。