研究论文
Simultaneous development of flow and temperature fields in wire-wrapped fuel pin bundles of sodium cooled fast reactor
N. Govindha Rasu, K. Velusamy, T. Sundararajan, P. Chellapandi
Indira Gandhi Centre for Atomic Research University of Madras Indian Institute of Technology Madras
来源Nuclear Engineering and Design
年份2013
阅读操作
确认中在文库中上传 PDF 后可生成中文音频讲解。
摘要与影响
摘要 · 节选
暂未获取摘要。可打开原文或 PDF，后续可基于全文生成更完整的速读。
逐年被引趋势
740
17
18
19
20
21
22
23
724
25
26
关键指标
42
被引次数 · OpenAlex
24.94
领域内被引倍数
同类平均 = 1
同类平均 = 1
前 1.0%
引用位次
同领域 · 同年份 · 同类型
同领域 · 同年份 · 同类型
36
参考文献
Google Scholar 与 OpenAlex 的被引统计范围不同，数值存在差异属正常。
AI 辅助阅读
依据：文献信息
论文问答
当前基于文献信息回答
可就本文提问；依据不足时会说明。
学术脉络
学科主题
工程Nuclear reactor physics and engineering
Heat transfer and supercritical fluids · Nuclear Engineering Thermal-Hydraulics
参考文献 36
Large eddy simulation of wire-wrapped fuel pins I: Hydrodynamics in a periodic array.
被引 36Paul Fischer, James Lottes, Andrew Siegel · 2007
Heat transfer to liquid metals in longitudinally wetted bundles of rods
被引 79V. M. Borishanskii, М. А. Готовский, �. V. Firsova · Atomic Energy · 1969
Laminar, Transition, and Turbulent Parallel Flow Pressure Drop Across Wire-Wrap-Spaced Rod Bundles
被引 91Felix Engel, R.A. Markley, A.A. Bishop · Nuclear Science and Engineering · 1979
此处列出前 3 条
引用本文 42
PIV measurements of turbulent flows in a 61-pin wire-wrapped hexagonal fuel bundle
被引 82Thien Nguyen, Nolan Goth, P. Jones · International Journal of Heat and Fluid Flow · 2017
A review of CFD studies on thermal hydraulic analysis of coolant flow through fuel rod bundles in nuclear reactor
被引 76Mingjun Wang, Haoran Ju, Wu Jian · Progress in Nuclear Energy · 2024
CFD investigation on thermal-hydraulic behaviors of a wire-wrapped fuel subassembly for sodium-cooled fast reactor
被引 75Jing Chen, Dalin Zhang, Ping Song · Annals of Nuclear Energy · 2017
按被引量排序，此处列出前 3 条