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题名

Numerical investigation of the migration and retention of corrosion particles in a lead-cooled fast reactor

作者
通讯作者Li,Xinggang
发表日期
2024-07-01
DOI
发表期刊
ISSN
0029-5493
卷号423
摘要
The lead–bismuth eutectic (LBE) coolant corrodes structural materials during nuclear reactor operations. The corrosion products accumulate and are deposited after long-term operations, blocking the narrow flow paths inside the reactor loop and reducing reactor performance. This study investigates the effects of the flow field and particle characteristics on the corrosion products. The discrete phase model was used to describe the movement of the corrosion products in the flow field. A lead-cooled fast reactor model was proposed to calculate the velocity and temperature fields of the single-phase flow for different mass flow rates of the LBE coolant. As the LBE velocity increased, the number of trapped particles and the coolant temperature in the reactor decreased. The particle size, density, and shape factor affected the particle movement. Particles with a small size (less than 75 μm), high particle density, or a small shape factor (more than 100 μm diameter) resulted in improved flow of the particles with the LBE coolant and lower particle retention rates in the fluid. As the particle size increased, the number of retained particles in the upper region and on the free surface of the reactor increased, whereas the number of particles reaching the pump outlet decreased.
关键词
相关链接[Scopus记录]
收录类别
SCI ; EI
语种
英语
学校署名
通讯
EI入藏号
20241615925178
EI主题词
Bismuth ; Corrosion ; Eutectics ; Fast reactors ; Flow fields ; Particle size
EI分类号
Metallography:531.2 ; Nonferrous Metals and Alloys excluding Alkali and Alkaline Earth Metals:549.3 ; Fission Reactors:621.1 ; Fluid Flow, General:631.1 ; Chemical Agents and Basic Industrial Chemicals:803
ESI学科分类
ENGINEERING
Scopus记录号
2-s2.0-85190253621
来源库
Scopus
引用统计
成果类型期刊论文
条目标识符http://sustech.caswiz.com/handle/2SGJ60CL/741055
专题工学院_材料科学与工程系
作者单位
1.Institute of Nuclear Materials,School of Materials Science and Engineering,University of Science and Technology Beijing,Beijing,100083,China
2.Department of Materials Science and Engineering,Southern University of Science and Technology,Shenzhen,518055,China
3.China Nuclear Power Technology Research Institute,Shenzhen,518000,China
通讯作者单位材料科学与工程系
推荐引用方式
GB/T 7714
Xu,Yishou,Li,Xinggang,Huang,Xiaodong,et al. Numerical investigation of the migration and retention of corrosion particles in a lead-cooled fast reactor[J]. Nuclear Engineering and Design,2024,423.
APA
Xu,Yishou.,Li,Xinggang.,Huang,Xiaodong.,Zhang,Xiaoxin.,Hu,Chen.,...&Yan,Qingzhi.(2024).Numerical investigation of the migration and retention of corrosion particles in a lead-cooled fast reactor.Nuclear Engineering and Design,423.
MLA
Xu,Yishou,et al."Numerical investigation of the migration and retention of corrosion particles in a lead-cooled fast reactor".Nuclear Engineering and Design 423(2024).
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