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Nuclear Energy Engeering

Zaiyong Ma

2020-04-21 10:44  点击:[]


Name

Zaiyong Ma

Department

Nuclear Science and Technology

Title

Associate Professor

Contact  Information

mazy@cqu.edu.cn

Biography:

As a doctor, master tutor and member of nuclear society, I graduated from the department of nuclear energy, Xi'an Jiaotong University in 2015. Later I worked in Shanghai Nuclear Engineering Research and Design Institute for one year. In 2017, I entered Chongqing University.

My research areas include nuclear thermo-hydraulics and safety, boiling, two-phase flow, phase transition, critical heat flux, flow instability, etc., which were supported by many organizations such as MOST, NSFC, SNERDI, NPIC, IAEA. Papers have been published in many important academic journals in this field at home and abroad (e.g., International Journal of Heat and Mass Transfer, Annals of Nuclear Energy, Nuclear Engineering and Design, Progress in Nuclear Energy, etc.). I am also a reviewer of many international academic journals in this field.

Education Background:

2006.8—2007.6             XJTU                                    Bioengineering      

2007.9—2010.6             XJTU                                    Nuclear                    Bachelor

2015.7—2015.11           Hokkaido University            Nuclear                   

2010.9—2015.12           XJTU                                    Nuclear                    Doctor

Research Interests:

System code development

Flow instability analysis

Two-phase flow

Critical heat flux

 

Research Grants

 Enrollment specialty: Nuclear science and engineering, Power engineering and engineering thermal-physics

 Enrollment type: Graduate student

Selected Publications

[1]. Zaiyong Ma*, Suizheng Qiu, Luteng Zhang, Shanshan Bu, Wan Sun, Liangming Pan. A best-estimated correlation for prediction of nucleation radius in sodium boiling. Nuclear Engineering and Design, 2019, 345: 40-46.

[2]. Zaiyong Ma*, Luteng Zhang, Shanshan Bu, Wan Sun, Deqi Chen, Liangming Pan. A study of the heat flux profile effect on parallel channel density wave oscillation in sodium heated heat exchanger. Progress in Nuclear Energy, 2019 ,112:135-145.

[3]. Zaiyong Ma*, Luteng Zhang, Wan Sun, Shanshan Bu, Liangming Pan. A study on the density wave oscillation relative stability turning point of uniform and cosine heat flux profiles in parallel channels. Annals of Nuclear Energy, 2019, 127:111-119.

[4]. Zhangrui Jiang, Zaiyong Ma*, Rungang Yan, Luteng Zhang, Wan Sun, Shanshan Bu, Liangming Pan. Experimental study on the flow boiling oscillation characteristics in a rectangular multiple micro-channel. Experimental Thermal and Fluid Science,109 (2019 ),109902.

[5]. Zaiyong Ma*, Tingpu Ye, Quanyao Ren, Liangming Pan, Shanshan Bu, Luteng Zhang, Wan Sun, Friction and local pressure loss characteristics of a 5×5 rod bundle with spacer grids. Annals of nuclear energy, 140(2020), 107106

[6]. Zhangrui Jiang, Zaiyong Ma, et al. Flow boiling patterns in rectangular multiple micro-channels. The 9th China-Korea Workshop on Nuclear Reactor Thermal-Hydraulics.

[7]. Zhangrui Jiang, Zaiyong Ma, et al. Time domain and frequency domain analysis of pressure drop in rectangular multiple micro-channels. The 9th China-Korea Workshop on Nuclear Reactor Thermal-Hydraulics.

[8]. Zhangrui Jiang, Zaiyong Ma, et al. Analysis of reversed flow in inverted U-tube steam generator under natural circulation conditions. The 9th China-Korea Workshop on Nuclear Reactor Thermal-Hydraulics.

[9]. Zhipeng Jiang, Wang Xu, Zaiyong Ma.Numerical simulation of evaporation and condensation of stagnant liquid sodium. The 9th China-Korea Workshop on Nuclear Reactor Thermal-Hydraulics.

[10]. Chu Tao,Yin Siyou,Ma Zaiyong,Jiang Zhangrui,Bu Shanshan. Numerical analysis of reverse flow in U-tube steam generator under natural circulation conditions.The 9th China-Korea Workshop on Nuclear Reactor Thermal-Hydraulics.

[11]. Zaiyong Ma, Dalin Zhang, Liangming PanThe heat flux distribution in a steam generator and its effects on flow instability characteristics. 2nd Sino-German Symposium on Fundamentals of Advanced Nuclear Safety Technology (SG-FANS), Germany, 2017. 9.12-9.15.

Conferences:

ICONE27, WORTH-9 etc.

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