研究论文

Thermal hydraulic design and mass optimization of a 100-kWe S-CO2 cooled Mars-surface fission reactor system

Qi Xue, Pan Wu, Ming Liu, Jianqiang Shan, Yanping Huang

Xi'an Jiaotong University　China National Nuclear Corporation　Nuclear Power Institute of China

来源Annals of Nuclear Energy

年份2023

DOI10.1016/j.anucene.2023.109893

原文https://doi.org/10.1016/j.anucene.2023.109893

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学术脉络

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Nuclear reactor physics and engineering

Thermodynamic and Exergetic Analyses of Power and Cooling Systems · Nuclear Engineering Thermal-Hydraulics

参考文献 21

Thermal hydraulic design of a 2400 MW th direct supercritical CO₂-cooled fast reactor

Michael A. Pope · DSpace@MIT (Massachusetts Institute of Technology) · 2006

被引 22

Prometheus Project Reactor Module Final Report, For Naval Reactors Information

MJ Wollman, MJ Zika · 2006

被引 32

Thermal-Hydraulic Analyses of the Submersion-Subcritical Safe Space (S∧4) Reactor

Jeffrey C. King, Mohamed S. El‐Genk · AIP conference proceedings · 2007

被引 15

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引用本文 13

Supercritical CO2 Brayton cycle for space exploration: New perspectives base on power density analysis

Yuzhuo Yang, Lingfeng Shi, Yu Yao · Energy · 2024

被引 20

Research Advances in the Application of the Supercritical CO2 Brayton Cycle to Reactor Systems: A Review

Yuhui Xiao, Yuan Zhou, Yuan Yuan · Energies · 2023

被引 16

Conceptual design and optimization of heat rejection system for nuclear reactor coupled with supercritical carbon dioxide Brayton cycle used on Mars

Jianxin Qiao, Shenghui Liu, Minyun Liu · Progress in Nuclear Energy · 2024

被引 14

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