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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
DOI
发表期刊
ISSN
1000-6931
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
学校署名
通讯
EI入藏号
20212010375782
EI主题词
Computerized tomography ; Containers ; Data handling ; Defects ; Fuels ; Monte Carlo methods ; Neutron radiography ; Neutrons ; Nondestructive examination ; Plate metal
EI分类号
Data Processing and Image Processing:723.2 ; Computer Applications:723.5 ; Mathematical Statistics:922.2 ; Materials Science:951
Scopus记录号
2-s2.0-85105845784
来源库
Scopus
引用统计
被引频次[WOS]:0
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.
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.
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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