World's Best Scientists 2026 revealed!

D-Index & Metrics

Engineering and Technology

D-Index
55
Citations
16631
World Ranking
2930
National Ranking
590

Overview

Suizheng Qiu is affiliated with Xi'an Jiaotong University in China, contributing extensively to the fields of engineering and materials science. Their research output spans multiple domains, including aerospace engineering, materials chemistry, mechanical engineering, computational mechanics, and biomedical engineering.

The primary research focus centers on nuclear reactor physics and engineering, with a significant emphasis on nuclear engineering thermal-hydraulics and nuclear materials and properties. Additional topics include heat transfer and boiling studies, heat transfer and supercritical fluids, heat transfer and optimization, and fusion materials and technologies.

Suizheng Qiu has published regularly in a variety of scientific venues. The most frequent publication outlets include:

  • Annals of Nuclear Energy
  • SSRN Electronic Journal
  • Progress in Nuclear Energy
  • Nuclear Engineering and Design
  • Applied Thermal Engineering

Recent publications feature the following works:

  • Recent progress of CFD applications in PWR thermal hydraulics study and future directions, 2020, Annals of Nuclear Energy
  • Two-phase bubbly flow simulation using CFD method: A review of models for interfacial forces, 2020, Progress in Nuclear Energy
  • Experimental study on heat pipe thermoelectric generator for industrial high temperature waste heat recovery, 2020, Applied Thermal Engineering
  • Fluoride-salt-cooled high-temperature reactors: Review of historical milestones, research status, challenges, and outlook, 2022, Renewable and Sustainable Energy Reviews
  • Experimental investigation on the heat transfer performance of high-temperature potassium heat pipe for nuclear reactor, 2021, Nuclear Engineering and Design

Collaboration is a notable part of Suizheng Qiu's academic work. Frequent co-authors include:

  • Wenxi Tian
  • G.H. Su
  • Chenglong Wang
  • Dalin Zhang
  • Mingjun Wang

Best Publications

  • Recent progress of CFD applications in PWR thermal hydraulics study and future directions

    Mingjun Wang;Yingjie Wang;Wenxi Tian;Suizheng Qiu

  • Fluoride-salt-cooled high-temperature reactors: Review of historical milestones, research status, challenges, and outlook

    Unknown

  • Applications of ANNs in flow and heat transfer problems in nuclear engineering: A review work

    Tenglong Cong;Guanghui Su;Suizheng Qiu;Wenxi Tian

  • Numerical investigation on coalescence of bubble pairs rising in a stagnant liquid

    R.H. Chen;W.X. Tian;W.X. Tian;G.H. Su;S.Z. Qiu

  • Two-phase bubbly flow simulation using CFD method: A review of models for interfacial forces

    Irfan Khan;Mingjun Wang;Yapei Zhang;Wenxi Tian

  • Review of conceptual design and fundamental research of molten salt reactors in China

    Dalin Zhang;Limin Liu;Minghao Liu;Rongshuan Xu

  • Metallurgical study on erosion and corrosion behaviors of steels exposed to liquid lead bismuth flow

    Unknown

  • Effects of turbulence models on forced convection subcooled boiling in vertical pipe

    Rui Zhang;Tenglong Cong;Wenxi Tian;Suizheng Qiu

  • Experimental study on heat pipe thermoelectric generator for industrial high temperature waste heat recovery

    Chenglong Wang;Simiao Tang;Xiao Liu;G.H. Su

  • Study on the characteristics of the sodium heat pipe in passive residual heat removal system of molten salt reactor

    Chenglong Wang;Dalin Zhang;Suizheng Qiu;Wenxi Tian

  • Isothermal experiments on steam oxidation of magnetron-sputtered chromium-coated zirconium alloy cladding at 1200℃

    Unknown

  • Analysis of safety margin of in-vessel retention for AP1000

    Y.P. Zhang;S.Z. Qiu;G.H. Su;W.X. Tian

  • Thermal hydraulic phenomena related to small break LOCAs in AP1000

    W.W. Wang;G.H. Su;S.Z. Qiu;W.X. Tian

  • Experimental Evaluation on Heat Transfer Limits of Sodium Heat Pipe with Screen Mesh for Nuclear Reactor System

    Unknown

  • Experimental study on startup performance of high temperature potassium heat pipe at different inclination angles and input powers for nuclear reactor application

    Chenglong Wang;Lirong Zhang;Xiao Liu;Simiao Tang

  • Natural convection heat transfer in corium pools: A review work of experimental studies

    Luteng Zhang;Yukun Zhou;Yapei Zhang;Wenxi Tian

  • Research on the designed emergency passive residual heat removal system during the station blackout scenario for CPR1000

    Mingjun Wang;Hao Zhao;Yapei Zhang;Guanghui Su

  • Numerical simulation and optimization on valve-induced water hammer characteristics for parallel pump feedwater system

    Wenxi Tian;G.H. Su;Gaopeng Wang;Suizheng Qiu

  • Multi-objective optimization of helical coil steam generator in high temperature gas reactors with genetic algorithm and response surface method

    Unknown

  • Flow blockage analysis of a channel in a typical material test reactor core

    Qing Lu;Suizheng Qiu;G.H. Su

  • A review on thermohydraulic and mechanical-physical properties of SiC, FeCrAl and Ti3SiC2 for ATF cladding

    Bowen Qiu;Jun Wang;Yangbin Deng;Mingjun Wang

  • A Review on Analysis of LWR Severe Accident

    Y. P. Zhang;S. P. Niu;L. T. Zhang;S. Z. Qiu

  • Numerical investigation on bubble dynamics during flow boiling using moving particle semi-implicit method

    Ronghua Chen;Wenxi Tian;G.H. Su;Suizheng Qiu

  • Development of a safety analysis code for molten salt reactors

    Dalin Zhang;Suizheng Qiu;Guanghui Su

  • CFD investigation on thermal-hydraulic behaviors of a wire-wrapped fuel subassembly for sodium-cooled fast reactor

    Jing Chen;Dalin Zhang;Ping Song;Xinan Wang

  • Performance analysis of heat pipe radiator unit for space nuclear power reactor

    Chenglong Wang;Jing Chen;Suizheng Qiu;Wenxi Tian

  • Conceptual design and analysis of a multipurpose micro nuclear reactor power source

    Hao Sun;Chenglong wang;Pan Ma;Xiao Liu

  • Experimental investigation on the heat transfer performance of high-temperature potassium heat pipe for nuclear reactor

    Zhixing Tian;Xiao Liu;Chenglong Wang;Dalin Zhang

Frequent Co-Authors

Guanghui Su
Guanghui Su Xi'an Jiaotong University
Michael L. Corradini
Michael L. Corradini University of Wisconsin–Madison
Yoshiaki Oka
Yoshiaki Oka University of Tokyo
Francis A Kulacki
Francis A Kulacki University of Minnesota
Dirk Lucas
Dirk Lucas Helmholtz-Zentrum Dresden-Rossendorf

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