背景:
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崔世杰


崔世杰,男,1992年出生,山东德州人,博士后。

 

教育背景:

2016.09-2019.12,西安交通大学,核科学与技术专业,工学博士

2014.09-2016.06,西安交通大学,核能与核技术工程专业,工程硕士

2010.09-2014.07,西安交通大学,核工程与核技术专业,工学学士

 

工作经历:

2022.04-至今,中科院等离子体物理研究所,助理研究员

2020.01-2022.04,深圳大学新能源研究中心李建刚院士工作站,博士后

 

研究方向:

主要从事聚变堆氚燃料循环和安全相关的科学问题和工程技术研究,以及中国聚变工程实验堆(CFETR)氦冷陶瓷增殖剂包层设计与中子学、热工水力学、结构力学等多物理场耦合分析优化研究。

 

科研项目情况:

1. 国家自然科学基金青年项目,《非均匀中子壁负载条件下CFETR氦冷固态包层多场耦合特性研究》,主持;

2. 中国博士后科学基金面上项目,《非均匀中子壁负载条件下CFETR氦冷固态包层氚输运特性研究》,主持;

3. 西安交通大学横向项目,《基于多物理场耦合的CFETR包层三维时空能量沉积及热工安全特性研究》,主持;

4. 中国科学院合肥物质科学研究院横向项目,《CFETR氦冷固态包层物理-热工耦合优化设计》,主持;

5. 国际热核聚变实验堆(ITER)计划专项项目,《中国聚变工程实验堆(CFETR)包层热工水力设计与安全分析评价研究》,项目骨干;

6. 国家磁约束核聚变能发展研究专项,《基于多物理场耦合的CFETR包层三维时空能量沉积及热工安全特性研究》,主要参与;

7. 国家磁约束核聚变能发展研究专项子课题,《CFETR装置总体集成和工程设计-氦冷包层的工程设计》,参与。

 

发表期刊论文:

[1] Shijie Cui, Dalin Zhang, Jie Cheng, et al. Numerical research on the neutronic/thermal-hydraulic/mechanical coupling characteristics of the optimized helium cooled solid breeder blanket for CFETR[J]. Fusion Engineering and Design, 2017, 114: 141-156.

[2] Shijie Cui, Dalin Zhang, Qiang Lian, et al. Evaluation and optimization of tritium breeding, shielding and nuclear heating performances of the helium cooled solid breeder blanket for CFETR[J]. International Journal of Hydrogen Energy, 2017, 42(38): 24263-24277.

[3] Shijie Cui, Dalin Zhang, Qiang Lian, et al. Development of a neutronics/thermal-hydraulic coupling optimization code and its application on the CFETR HCSB blanket[J]. Fusion Engineering and Design, 2017, 122: 140-153.

[4] Shijie Cui, Dalin Zhang, Jian Ge, et al. Development and application of a neutronics/thermal-hydraulics coupling optimization code for the CFETR helium cooled solid breeder blanket with mixed pebble beds[J]. Fusion Engineering and Design, 2017, 125: 24-37.

[5] Shijie Cui, Dalin Zhang, Xinli Gao, et al. Conceptual design and comprehensive optimization analysis of a fusion-fission hybrid reactor water-cooled pressure tube blanket[J]. Progress in Nuclear Energy, 2018, 103: 8-19.

[6] Shijie Cui, Dalin Zhang, Wenxi Tian, et al. Numerical research on the coupling optimization design rule of the CFETR HCSB blanket using the NTCOC code[J]. Fusion Engineering and Design, 2018, 127: 234-248.

[7] Shijie Cui, Dalin Zhang, Yueheng Lang, et al. A new method for improving the tritium breeding and releasing performance of China Fusion Engineering Test Reactor phase II helium-cooled ceramic breeder blanket[J]. International Journal of Energy Research, 2020, 44(7): 5977-5989.

[8] Shijie Cui, Dalin Zhang, Yueheng Lang, et al. Preliminary design and analyses of the helium cooled ceramic breeder blanket for CFETR phase II[J]. International Journal of Energy Research, 2021, 45(8): 11598-11615.

[9] Shijie Cui, Yueheng Lang, Dalin Zhang, et al. Three-dimensional validation and analyses of the optimized CFETR HCCB blanket[J]. Fusion Engineering and Design, 2020, 161: 111971.

[10] Shijie Cui, Yueheng Lang, Qiang Lian, et al. Preliminary thermal-hydraulic influence of the poloidal nonuniform neutron wall loading on the CFETR HCCB blanket[J]. Fusion Engineering and Design, 2021, 165: 112232.

[11] Shijie Cui, Yueheng Lang, Qiang Lian, et al. Neurtonics/Thermal-hydraulic analyses of the CFETR HCCB blanket for multiple operation modes under the poloidal nonuniform neutron wall loading condition[J]. Fusion Engineering and Design, 2021, 168: 112612.

[12] Dalin Zhang, Shijie Cui, Jie Cheng, et al. Improving the optimization algorithm of NTCOC for application in the HCSB blanket for CFETR Phase II[J]. Fusion Engineering and Design, 2018, 135: 216-227.

[13] Qiang Lian, Shijie Cui, Wenxi Tian, et al. Preliminary accident analysis of Loss of Off-Site Power and In-Box LOCA for the CFETR helium cooled solid breeder blanket[J]. Fusion Engineering and Design, 2017, 118: 142-150.

[14] Qiang Lian, Wenxi Tian, Shijie Cui, et al. Preliminary safety assessment on two LOCAs under ITER-like condition for the optimized CFETR helium cooled solid breeder blanket[J]. Fusion Engineering and Design, 2017, 121: 235-244.

[15] Jie Cheng, Yingwei Wu, Shijie Cui, et al. Conceptual design and coupled neutronic/thermal-hydraulic/mechanical research of the supercritical water cooled ceramic blanket for CFETR[J]. Fusion Engineering and Design, 2019, 138: 272-281.

[16] Mingjun Wang, Yan Xiang, Shijie Cui, et al. Numerical study on the purge gas flow and heat transfer characteristics in helium cooled solid breeder blanket of CFETR[J]. Progress in Nuclear Energy, 2018, 105: 114-123.

[17] Mingjun Wang, Di Liu, Yan Xiang, Shijie Cui, et al. Experimental study of the helium flow characteristics in pebble-bed under the condition of CFETR's blanket module[J]. Progress in Nuclear Energy, 2017, 100: 283-291.

 

获得奖励:

[1] 西安交通大学2016届优秀毕业生(2016年3月)

[2] “希捷-小平基金”科技创新奖学金(2018年1月)

[3] 西安交通大学优秀共产党员(2018年10月)

[4] 博士研究生国家奖学金(2018年11月)

[5] Fusion Engineering and Design期刊“Most cited paper”(2019年5月)

[6] 西安交通大学2019届优秀毕业研究生干部(2019年12月)

[7] 深圳大学李建刚院士工作站优秀博士后(2021年9月)

[8] JANDT(International Journal of Advanced Nuclear Reactor Design and Technology)国际期刊青年编委