*个人简介：

男，山东淄博人，重庆大学动力工程学院核能工程系，副教授。

联系方式：mazy@cqu.edu.cn

办公室地址：重庆大学A区动力大楼415室

*教育经历：

2015.07—2015.11     北海道大学，访问学者

2010.09—2015.12     西安交通大学 核能系，硕博连读

2007.09—2010.06     西安交通大学 核能系，学士

2006.08—2007.06     西安交通大学 生物工程系，本科

*研究方向：

1.液态金属热工水力实验研究，机理模型和关系式开发

2.钠冷快堆通用系统安全分析程序开发及V&V

3.钠水蒸汽发生器双侧耦合流动不稳定性分析

4.熔融金属滴落扩展行为的Star-CCM+模拟

5.子通道分析

*发表论文：

1. Zaiyong Ma, Yingwei Wu, Zicheng Qiu, Wenxi Tian, Guanghui Su, Suizheng Qiu. An innovative method for prediction of liquid metal heat transfer rate for rod bundles based on annuli. Annals of Nuclear Energy, 2012, 47, 91-97.

2. Zaiyong Ma, Zicheng Qiu, Yingwei Wu, Suizheng Qiu, Guanghui Su. An analysis of incipient boiling superheat in alkali liquid metals. International Journal of Heat and Mass Transfer, March 2014, 70, 526-535.

3.Zaiyong Ma, Zicheng Qiu, Yingwei Wu, Suizheng Qiu, Guanghui Su, Wenxi Tian. Analysis of heat flux and velocity effects on nucleation superheat in liquid metals based on dynamic effects. Annals of Nuclear Energy, 2014, 72, 39-48.

4. Zaiyong Ma, Nina Yue, Meiyin Zheng, Benxue Hu, Guanghui Su, Suizheng Qiu. Basic verification of THACS for sodium-cooled fast reactor system analysis. Annals of Nuclear Energy, 2015, 76: 1-11.

5. Zicheng Qiu, Zaiyong Ma, Suizheng Qiu, Yingwei Wu, Wenxi Tian, Guanghui Su, Dalin Zhang. Experimental research on the incipient boiling wall superheat of sodium. Progress in Nuclear Energy, 2013, 68, 121-129.

6. Zicheng Qiu, Zaiyong Ma, Yingwei Wu, Suizheng Qiu, Guanghui Su. Experimental research on the thermal hydraulic characteristics of liquid sodium flowing in annuli with low Peclet number. Annals of Nuclear Energy, 2015, 75,483-491.

7. Zicheng Qiu, Zaiyong Ma, Suizheng Qiu, Guanghui Su, Zhang Dalin, Yingwei Wu, Wenxi Tian. Experimental research on the thermal hydraulic characteristics of sodium boiling in an annulus. Experimental Thermal and Fluid Science, 2015, 60: 263-274.

8. Wenwen Zhang, Zaiyong Ma, Dalin Zhang, Wenxi Tian, Suizheng Qiu, Guanghui Su. Transient thermal-hydraulic analysis of a space thermionic reactor. Annals of Nuclear Energy, 2016, 89: 38-49.

9. Nina Yue, Zaiyong Ma, Rong Cai, Benxue Hu, G.H. Su, S.Z. Qiu. Thermal-hydraulic analysis of EBR- II shutdown heat removal tests SHRT-17 and SHRT-45R. Progress in Nuclear Energy, 2015:682–693.

10. 张文文, 陈静, 王成龙, 马在勇, 田文喜, 秋穗正, 苏光辉.热管改进型热离子反应堆瞬态分析程序开发[J].原子能科学技术,2015,49(z1):227-233.

11. 马在勇,仇子铖,王美,田文喜,苏光辉,秋穗正. 液态金属棒束传热的理论分析. 原子能科学技术,2011,12:1478-1483. (EI)

12. 马在勇,仇子铖,巫英伟,田文喜,苏光辉,秋穗正. 液膜蒸干模型在液态金属CHF预测中的应用. 原子能科学技术,2014,48：617-62.(EI)

13. Zaiyong Ma, Nina Yue, Dalin Zhang, Yingwei Wu, Suizheng Qiu. Simulation of EBR-II SHRT-17 and SHRT-45R Tests with THACS. 8th Joint  International  Symposium  on Nuclear  Science and Technology XJTU-UT-SJTU Joint Workshop, Tokai, Japan, Jul. 26-29, 2015

14. Ma Zaiyong, Zhang Dalin, Wu Yingwei, Tian Wenxi, Qiu Suizheng, Su Guanghui. Study on Typical Flow Instability Conditions in Modular Sodium-water Steam Generator, The Seventh China-Korea Workshop on Nuclear Reactor Thermal-Hydraulics, WORTH-7, Kunming, China, 2015.

15. Zaiyong Ma, Yue Nina, Suizheng Qiu, Guanghui Su, Wenxi Tian. Application of Film Dryout Model in Liquid Metal CHF Prediction, Proceedings of the 2014 22nd International Conference on Nuclear Engineering, ICONE22, 2014.07. (EI)

16. Yue Nina, Ma Zaiyong, Hu Benxue, Suizheng Qiu, Guanghui Su. Validation of Thacs for Sodium Cooled Fast Reactor Based on Benchmark Analysis of EBR-II, Proceedings of the 2014 22nd International Conference on Nuclear Engineering, ICONE22, 2014.07. (EI)

17. Zicheng Qiu, Zaiyong Ma, Suizheng Qiu, Yingwei Wu, Guanghui Su. Experimental study on the thermal hydraulic characteristics of liquid sodium flowing in an annulus. 22nd International Conference on Nuclear Engineering, ICONE22, 2014.07. (EI)

18. 岳倪娜, 马在勇, 蔡容等. 钠冷快堆事故不确定性分析. 第十四届全国反应堆热工流体学术会议暨中核核反应堆热工水力技术重点实验室2015年度学术年会论文集. 2015.

19. 马在勇, 岳倪娜, 扈本学, 秋穗正, 苏光辉, 巫英伟. 钠冷快堆程序THACOS的无保护失流事故基准题验证. 第十三届全国反应堆热工流体学术会议, 2013.04.06.

20. 岳倪娜, 马在勇, 扈本学, 秋穗正, 苏光辉. 钠冷快堆系统程序的EBR-II基准题验证. 第十三届全国反应堆热工流体学术会议, 2013.04.06.