题名 | Study on Indirect Neutron CT Technology of Nuclear Fuel Element Based on Neutron IP Plate 基于中子IP板的核燃料元件间接中子CT实验方法研究 |
作者 | |
通讯作者 | Han,Songbai; Chen,Dongfeng |
发表日期 | 2021-05-20
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DOI | |
发表期刊 | |
ISSN | 1000-6931
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卷号 | 55期号:5页码:939-944 |
摘要 | Neutron radiography, an effective non-destructive testing technology, is an important means to analyze and determine the defects inside nuclear fuel elements. Based on the neutron radiography platform located at China Advanced Research Reactor (CARR), the neutron radiography group at China Institute of Atomic Energy has carried out the research on the simulated nuclear fuel elements using the developed indirect three-dimensional neutron imaging device for nuclear fuel elements. The key parameters of sample transfer container for nuclear fuel elements were optimized and the container was designed based on the Monte Carlo simulation method. As a result, the study on simulated sample of nuclear fuel elements was performed using the developed indirect three-dimensional neutron imaging device, and the defects with the size of about 0.35 mm can be clearly observed in the obtained reconstructed 3D images. Therefore, the experimental results indicate that this developed device at CARR can meet the demand of studying nuclear fuel elements. Besides, several factors and processing methods for indirect neutron CT experimental digital images during data processing were also studied simultaneously, and this study can provide some invaluable advice for practical application of real nuclear fuel elements using metal conversion screen to replace the neutron image plate (IP) in this study in future. |
关键词 | |
相关链接 | [Scopus记录] |
收录类别 | |
语种 | 中文
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学校署名 | 通讯
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EI入藏号 | 20212010375782
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EI主题词 | Computerized tomography
; Containers
; Data handling
; Defects
; Fuels
; Monte Carlo methods
; Neutron radiography
; Neutrons
; Nondestructive examination
; Plate metal
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EI分类号 | Data Processing and Image Processing:723.2
; Computer Applications:723.5
; Mathematical Statistics:922.2
; Materials Science:951
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Scopus记录号 | 2-s2.0-85105845784
|
来源库 | Scopus
|
引用统计 |
被引频次[WOS]:0
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成果类型 | 期刊论文 |
条目标识符 | http://sustech.caswiz.com/handle/2SGJ60CL/228432 |
专题 | 前沿与交叉科学研究院 |
作者单位 | 1.China Institute of Atomic Energy,Beijing,102413,China 2.China National Nuclear Corporation,Beijing,102413,China 3.Southern University of Science and Technology,Shenzhen,518055,China |
通讯作者单位 | 南方科技大学 |
推荐引用方式 GB/T 7714 |
Liu,Xiaoguang,He,Linfeng,Wu,Meimei,等. Study on Indirect Neutron CT Technology of Nuclear Fuel Element Based on Neutron IP Plate 基于中子IP板的核燃料元件间接中子CT实验方法研究[J]. 原子能科学技术,2021,55(5):939-944.
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APA |
Liu,Xiaoguang.,He,Linfeng.,Wu,Meimei.,Wei,Guohai.,Li,Zhengyao.,...&Chen,Dongfeng.(2021).Study on Indirect Neutron CT Technology of Nuclear Fuel Element Based on Neutron IP Plate 基于中子IP板的核燃料元件间接中子CT实验方法研究.原子能科学技术,55(5),939-944.
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MLA |
Liu,Xiaoguang,et al."Study on Indirect Neutron CT Technology of Nuclear Fuel Element Based on Neutron IP Plate 基于中子IP板的核燃料元件间接中子CT实验方法研究".原子能科学技术 55.5(2021):939-944.
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条目包含的文件 | ||||||
文件名称/大小 | 文献类型 | 版本类型 | 开放类型 | 使用许可 | 操作 | |
基于中子IP板的核燃料元件间接中子CT实(1349KB) | -- | -- | 限制开放 | -- |
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