个人简历

一、个人简介
周瑜琨，男，1991年9月生，江西吉安人。2011年本科毕业于西安交通大学核工程与核技术专业，2012年硕士毕业于西安交通大学核能科学与工程专业，2016年进入东华理工大学任教，目前正在西安交通大学核科学与技术专业攻读博士学位。负责《核反应堆安全》、《核反应堆热工水力学》等本科生教学工作。
主要科研项目
华龙一号堆芯熔融物传热特性数据采购，J20180416，中广核研究院有限公司，已结题，主要完成人；
严重事故下大型熔融池换热特性研究，HT-KFKT-02-2016011，中国核动力研究设计院，已结题，主要完成人；
专著与专利
[1] 核反应堆安全壳碎片迁移特性试验系统及其试验方法，张亚培，周瑜琨，巫英伟，苏光辉，田文喜，秋穗正，专利号：ZL 2018 1 1032363.8, 发明专利.

研究领域

主要研究方向为核反应堆热工水力计算和核电厂严重事故分析

近期论文

近几年公开发表的学术论文
[1]Yukun Zhou, Yapei Zhang, Simin Luo, et al. Results of simulant effect on large corium pool behavior based on COPRA facility [J]. Progress in Nuclear Energy, 108 (2018) 398-408.
[2]Yukun Zhou, Yapei Zhang, Kui Zhang, et al. Experimental study on natural convection heat transfer in a two-layer corium pool based on COPRA facility [J]. Nuclear Engineering and Design, 349 (2019) 136-143.
[3]Luteng Zhang, Yukun Zhou, Simin Luo, et al. Large eddy simulation for the thermal behavior of one-layer and two-layer corium pool configurations in HPR1000 reactor [J]. Applied Thermal Engineering, 145 (2018) 38-47.
[4]Simin Luo, Yapei Zhang, Yukun Zhou, et al. COPRA experiment and numerical research on the behavior of internally-heated melt pool with eutectic salt [J]. Applied Thermal Engineering, 140 (2018) 313-324.
[5]Zhang LT, Zhou YK, Zhang YP, et al. Natural convection heat transfer in corium pools: A review work of experimental studies[J]. Progress in Nuclear Energy, 2015, 79: 167-181.
[6]Zhang LT, Zhang YP, Zhou YK, et al. COPRA experiments on natural convection heat transfer in a volumetrically heated slice pool with high Rayleigh numbers[J]. Annals of Nuclear Energy, 2016, 87: 81-88.
[7]Yukun Zhou, Yapei Zhang, Simin Luo, et al. COPRA experiment on melt pool behavior with eutectic NaNO3-KNO3 simulant [C]. 2018 26th International Conference on Nuclear Engineering (ICONE26), London, England, July 22-26, 2018.
[8]Yukun Zhou, Shihao Wu, Zhiyu Yu, et al. Results of COPRA two-layer experiment on molten pool behavior [C]. 9th China-Korea Workshop on Nuclear Reactor Thermal-Hydraulics (WORTH-9), Chongqing, China, May 15-18, 2019.
[9]张卢腾，马如冰，周瑜琨等．高瑞利数下熔融池换热特性试验研究[J]．原子能科学技术，50(5)：798-804．
[10]张卢腾，张亚培，周瑜琨等．硬壳对熔融池换热特性影响试验研究[J]．原子能科学技术，50(6)：1002-1007