研究论文
Thermal hydraulic analysis of a pebble-bed modular high temperature gas-cooled reactor with ATTICA3D and THERMIX codes
Yanhua Zheng, J. Lapins, Eckart Laurien, L. Shi, Z. Zhang
Tsinghua University University of Stuttgart
来源Nuclear Engineering and Design
年份2012
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学科主题
工程Nuclear reactor physics and engineering
Nuclear Engineering Thermal-Hydraulics · Heat transfer and supercritical fluids
参考文献 17
International Atomic Energy Agency
被引 3,912Permanent missions to the United Nations · 2022
The TINTE Modular Code System for Computational Simulation of Transient Processes in the Primary Circuit of a Pebble-Bed High-Temperature Gas-Cooled Reactor
被引 75H. Gerwin, W. Scherer, E. Teuchert · Nuclear Science and Engineering · 1989
A Personal Computer-Based Simulation-and-Control-Integrated Platform for 10-MW High-Temperature Gas-Cooled Reactor
被引 8Lei Shi, Haibin Liu, Xiaojing Yang · Nuclear Technology · 2004
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引用本文 42
Numerical simulation of heat transfer in packed pebble beds: CFD-DEM coupled with particle thermal radiation
被引 184Hao Wu, Nan Gui, Xingtuan Yang · International Journal of Heat and Mass Transfer · 2017
Effect of scale on the modeling of radiation heat transfer in packed pebble beds
被引 89Hao Wu, Nan Gui, Xingtuan Yang · International Journal of Heat and Mass Transfer · 2016
A smoothed void fraction method for CFD-DEM simulation of packed pebble beds with particle thermal radiation
被引 65Hao Wu, Nan Gui, Xingtuan Yang · International Journal of Heat and Mass Transfer · 2017
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