个人信息
科学研究
教育教学
论著成果
研究团队

王翔

Wang Xiang

部门：核科学与技术学院

学科：核科学与技术

职务：

职称：副教授

指导资格：博士生导师
硕士生导师

电话： -

传真： -

邮箱： xiang.wang@hrbeu.edu.cn

邮编： 150001

地址：

个人简介

省部级人才。主要研究方向为先进核反应堆的多物理耦合研究、基于加速器与辐射的核技术应用、低碳能源发展应用研究。2013-2017于德国慕尼黑工业大学攻读核工程专业工学博士学位，2016-2017年于德国慕尼黑工业大学核工程系任全职研究人员。曾参与德国意昂（E.ON）集团核电部门先进熔盐堆研究项目，博士论文《Analysis And Evaluation Of The Dual Fluid Reactor Concept》作为项目报告出版为学术专著。主持并参与多项国家、省部级以及横向研究项目，发表学术论文70余篇，其中SCI检索20篇；申请核反应堆相关设计专利20余项，获发明专利11项，软件著作权4项。目前为《International Journal of Energy Research》《Annals of Nuclear Energy》《Nuclear Science and Techniques》等行业期刊审稿人。主讲《核物理与辐射安全》、《核反应堆物理》、《量子力学》等多门专业课程。目前与德国慕尼黑工业大学、亚琛应用技术大学、斯图加特大学、德国普鲁士电力有限公司、波兰国家核能研究中心、波兰什切青大学等多所高校和研究机构展开科研合作。

欢迎有兴趣的同学和老师联系，加入团队的科研工作与学术交流中。

教育经历

2013.01-2017.07 德国慕尼黑工业大学核工程专业博士（Dr.-Ing.）
2010.09-2011.04 法国国立核学院（INSTN）交换课程
2010.03-2012.12 德国慕尼黑工业大学核工程专业硕士（M.Sc.）
2009.03-2010.03 德国达姆施塔特工业大学物理系德语及预科
2004.09-2008.08 清华大学工程物理专业学士（B.-Eng.）

工作经历

2017.11～至今哈尔滨工程大学核科学与技术学院 新型反应堆的设计、计算与验证 副教授

2016.03～2017.09 德国慕尼黑工业大学核工程系 双流熔盐堆的设计、计算与验证 全职研究人员

2011.10～2012.10 德国反应堆安全协会（GRS）严重事故部 小型模块化压水堆的运行与事故工况的安全分析 研究人员

2011.07～2011.09 德国慕尼黑工业大学核工程系 小型模块化压水堆的事故分析与余热排出 学术科研助理

2010.06～2011.06 德国慕尼黑工业大学核工程系 小型模块化压水堆的设计与验证 学生科研助理

2008.02～2008.12 清华大学汤姆逊X射线光源设施 脉冲调制器的测试与低水平射频部件的设计 学生

2006.09～2008.02 清华大学工程物理系量子测控实验室 紫外激光光刻与穆斯堡尔效应测量 学生

研究方向

先进核反应堆（小型模块化反应堆、熔盐铅基堆、热管堆等）多物理耦合研究
1. 应用场景分析与堆芯设计
2. 堆芯中子物理计算
3. 热工水力CFD模拟计算
4. 概念验证与安全分析

基于加速器与辐射的核技术应用
1. 束流光学系统的数值模拟
2. 核泵浦激光的数值模拟
3. 特种核设施的辐射防护与屏蔽设计
4. 核医学剂量与治疗方案研究

低碳能源发展应用研究
1. 核燃料循环体系与经济学研究
2. 多种能源综合利用系统分析

承担项目

进行中

2022-2025 燃料棒设计与分析技术研究，省部级项目，36万元，负责人
2020-2022 新型深海铅铋合金冷却反应堆核动力系统研发，国家重点研发计划，831万元，主要参与人

2023-2025 事故工况下铅铋环境裂变产物行为及模拟研究，中国核动力研究设计院，50/165万元，课题负责人
2022-2023 铅铋快堆屏蔽设计相关技术，中广核研究院有限公司，50万元，负责人

2022-2023 大晶粒裂变气体释放机理与模型研究，中广核研究院有限公司，33万元，参与

2022-2023 龙码软件系统在液态金属冷却快堆中的应用与分析研究，西安交通大学，48万元，负责人

2022-2023 基于GPU的先进组件截面计算方法研究，中广核研究院有限公司，96万元，负责人

已结题
2020-2022 小型双流熔盐铅基堆的无棒系统稳定性机理及其控制，国家自然科学基金青年基金项目，27万元，负责人
2019-2022 双流熔盐堆无棒控制系统基础研究，黑龙江省自然科学基金优秀青年项目，10万元，负责人

2021-2022 快堆燃料性能分析软件二次开发及功能拓展项目，中广核研究院，33万元，主要参与人
2021-2022 医用一次性防护服化学灭菌的辐射替代，黑龙江省省属科研院所科研业务费，30万元，参与
2021-2021 核动力飞行器人工辐射特性与防护优化研究，省部级项目，20万元，主要参与人
2021-2021 并行离散纵标-非结构网格间断有限元中子输运计算软件测试，西安交通大学，10万元，负责人
2021-2021 新能源发电产业在县域（农村）扶贫、助产中的可行性研究，金科新能源有限公司，20万元，负责人
2020-2022 基于Modelica语言半物理核动力工程船舶模型仿真技术研究，中国核动力研究设计院，30万元，主要参与人
2020-2021 基于Modelica仿真的热管-热电转换耦合系统响应机理研究，中国核动力研究设计院重点实验室基金，28万元，负责人
2019-2020 核燃料循环情景与过程分析，中国原子能科学研究院，其他，148万元，主要参与人
2018-2020 双流熔盐堆的噪声分析，黑龙江省博士后资助经费，7万元，负责人

2019-2019 双流堆-热光电反应系统初步研究，黑龙江省留学回国人员择优资助项目，其他，5万元，负责人
2018-2019 核动力飞行器总体方案和数字样机研究，省部级项目，20万元，主要参与人

2018-2018 双流熔盐堆的基础研究I，中央高校基本科研业务费，10万元，负责人

2013-2017 Safety Analysis of the Molten Salt Reactor，德国意昂集团核电部门，18万欧元，主要参与人

学术交流

2019.06.17-19 受邀作为观察员赴摩洛哥参加IAEA非洲教育与培训机构副长与代表地区会议
2020.06.01-05 受邀在线在波兰国家核电中心组织的PhD4GEN高温堆夏令营上做报告
2020.07.15-19 举办在线中欧高校新核能（NewNuclear）夏令营
2020.10.13-15 受邀在线作为观察员参加IAEA人力资源会议
2022.09.05-10 受邀在线作为NUTHOS-13会议的Panelist

招生信息

自2019年起招收如下方向硕士研究生：
1、先进反应堆多物理耦合分析（核物理、反应堆物理、热工水力、计算机）
2、基于加速器与辐射的核技术应用（加速器、辐射屏蔽与防护、核医学）
3、低碳能源发展应用研究（核燃料循环、新能源）

自2023年起招收如下方向（暂定）博士研究生：
1、先进反应堆多物理耦合分析（核物理、反应堆物理、热工水力、计算机）
2、基于加速器与辐射的核技术应用（加速器、辐射屏蔽与防护、核医学）
3、低碳能源发展应用研究（核燃料循环、新能源）

本科生授课课程

2019起，《量子力学》《核反应堆物理》《核电子学》
2020起，《原子核物理基础》《辐射探测与防护》

研究生授课课程

2019起，《反应堆物理数值计算》《高等反应堆物理》
留学生研究生课程：
2017起，《Nuclear Physics》
2018起，《Reactor Physics》《Radiation Protection and Environment》

实践性教学

2019-2021 与德国慕尼黑工业大学共建课程《Radiation Protection and Environment》
2020-2022 全英文品牌研究生课程建设《Reactor Physics》
2020-2022 校级研究生在线课程建设《Radiation Protection and Environment》

教学研究课题

省级教改项目
2023-2024 新工科背景下核学科双创课程体系研究，负责人
2020-2021 “核能法跨学科特色课程教学体系构建研究”，参与
2019-2020 ““一带一路”建设背景下复合型高端核电人才培养体系研究”，参与
2019-2020 “核工程类专业拔尖创新人才培养模式的探索与实践——以哈尔滨工程大学“核创班”为例”，参与
校级教改项目
2019-2020 “核工程专业留学生研究生的教学探索”，负责人

社会兼职

专利成果

专利（11）

ZL2019110876804，一种具有可变屏蔽层的新型集装箱辐射防护装置，2021，1/2

ZL2019111744605，一种基于悬浮型核能供电声呐点阵单元的点阵系统，2022，2/6

ZL2020106080448，一种球型裂变核反应堆堆芯，2022，1/1

ZL2020104673523，一种液态燃料自持更新模块装置，2022，1/1

ZL2019111733884，一种悬浮型核能供电声呐点阵单元，2022，2/6

ZL2019111744588，一种固定型核电池供能声呐点阵单元及点阵系统，2022，2/6

ZL2019100858388，一种展开式核反应堆堆芯，2022，1/1

ZL2019101265765，一种分离式核反应堆堆芯，2019，1/1

ZL2019102900286，一种通过惯性力实现工作的液态燃料核反应堆，2019，1/6

ZL2019106943149，一种径向模块化反应堆，2019，1/1

ZL2019102900106，一种热管径向布置的核反应堆，2019，1/5

软件著作权（4）
2021SR0399717, 基于BP神经网络的一维点核积分屏蔽计算程序，2021，2/2

2021SR0986007，反应堆棒束结构中子物理与热工水力耦合计算框架软件，2021，2/2

2021SR1244271，基于MCNP的smDFR堆芯计算软件，2021，2/2

2022SR1496974，基于Modelica语言的核动力船舶动力系统半物理仿真平台，2022，2/2

出版著作

撰写（1）
1. 《Analysis and Evaluation of the Dual Fluid Reactor Concept》，ISBN: 978-620-2-32063-4, Südwestdeutscher Verlag für Hochschulschriften, 2017.
翻译（2）
2. 吕娜，寿文超，周磊，王翔. 《建筑的历史》，ISBN: 978-780-7-308775, 学林出版社，2009. (《Wie die Häuser in den Himmel wuchsen》, Susanna Partsch)
1. 吕娜，王文君，李秀青，翔西. 《心理学史》，ISBN: 978-780-7-308850, 学林出版社，2009. (《Geschichte der Psychologie》, Helmut E. Lück)

发表论文

期刊（20）

(2023)
20. Carolina Introini, Davide Chiesa, Massimiliano Nastasi, Ezio Previtali, Andrea Salvini, Monica Sisti, Xiang Wang, Antonio Cammi. A Complete CFD Study on Natural Convection in the TRIGA Mark II Reactor [J]. Nuclear Engineering and Design, 403(2023): 112118. doi: 10.1016/j.nucengdes.2022.112118.
(2022)

19. Songyang Liu, Tian Zhang, Xiang Wang*. Steady-state analyses of an smDFR with coupled Serpent-OpenFOAM calculation [J]. Nuclear Engineering and Design, 396(2022): 111892. doi: 10.1016/j.nucengdes.2022.111892.2.

18. Jinchao Zhang, Qian Zhang, Qiang Zhao, Xiang Wang. Surrogate model of predicting eigenvalue and power distribution by convolutional neural network [J]. Frontiers in Energy Research. 10(2022). doi: 10.3389/fenrg.2022.851231.

17. Runkai Chen, Marcus Seidl, Xiang Wang*. Core Design Optimization of Small Modular Dual Fluid Reactor based on NSGA-III in the Aspect of Reactor Physics [J]. Annals of Nuclear Energy, 174(2022): 109194. doi: 10.1016/j.anucene.2022.109194.

16. Yuxuan Liang, Bing Lan, Qian Zhang, Marcus Seidl, Xiang Wang*. Neutronic Analysis of Silicon Carbide Cladding-ATF Fuel Combinations in Small Modular Reactors [J]. Annals of Nuclear Energy， 173(2022): 109120. doi: 10.1016/j.anucene.2022.109120.

15. Yantao Luo, Tian Zhang, Xiang Wang*. Neutronic Analysis of the Unfolding Process of the LOTUS Reactor Design [J]. Annals of Nuclear Energy, 173(2022): 109102. doi: 10.1016/j.anucene.2022.109102

(2021)

14. Mingyue Wang, Xun He, Rafael Macian-Juan, Xiang Wang*. One-Dimensional Transient Analysis of the Dual-Fluid Reactor System [J]. Annals of Nuclear Energy, 162(2021): 108481. doi: 10.1016/j.anucene.2021.108481.

13. Runkai Chen, Antonio Cammi, Marcus Seidl, Rafael Macian-Juan, Xiang Wang*. Calculation of gamma-ray exposure build-up factor based on backpropagation neural network [J]. Expert Systems with Applications, 177(2021): 115004, 2021. doi: 10.1016/j.eswa.2021.115004.

(2020)

12. Andrea Di Ronco, Francesca Giacobbo, Guglielmo Lomonaco, Stefano Lorenzi, Xiang Wang, Antonio Cammi*. Preliminary Analysis and Design of the Energy Conversion System for the Molten Salt Fast Reactor [J]. Sustainability, 12(2020): 10497. doi: 10.3390/su122410497.

11. Qiang Yan, Zhongwen Chen, Zhijun Wang, Defeng Kong, Xiang Wang, Fujun Gou, Kun Zhang. Numerical Calculation on Recycling Ratio of Tritium from Tungsten Wall Used in Current CFETR Design [J]. Journal of Fusion Energy, 39(2020): 163-177. doi: 10.1007/s10894-020-00247-4.

10. Mingyue Wang, Liping Huang, Qian Zhang, Marcus Seidl, Zijing Liu*, Xiang Wang*. Preliminary Study on Physical Characteristics of Single-pass Super-critical Water-Cooled Reactor Core [J]. International Journal of Energy Research, 2020(45)8; p.11807-11821. doi: 10.1002/er.5764

9. Y. F. Zhang, Qian Zhang*, S. Li, Y. C. Liang, L. Lou, Xiang Wang, Q. Zhao, Z. J. Zhang. Evaluation of Burnup Calculation for Double-Heterogeneity System based on Sanchez-MOC framework in LWR [J]. Annals of Nuclear Energy, 147(2020): 107668. doi: 10.1016/j.anucene.2020.107668.

8. Y. C. Liang, Q. Zhang*, S. Li, L. Liang, Xiang Wang, Q. Zhao, L. Lou. Investigation of the Chord Length Markovian Probability Distribution for Self-Shielding Treatment on Double Heterogeneity Problem [J]. Annals of Nuclear Energy, 146(2020): 107658. doi: 10.1016/j.anucene.2020.107658.

7. Y. F. Zhang, Q. Zhang, J. C. Zhang, X. Wang, L. Lou, G. M. Liu, Q. Zhao, Z. J. Zhang. A comprehensive evaluation of the RPT method on FCM fuel in light water reactor [J]. Annals of Nuclear Energy, 142(2020): 107343. doi: 10.1016/j.anucene.2019.107434.

6. Q. Zhang*, J. Yu, J. C. Zhang, X. Wang, L. Liang. Investigation on the Depletion Calculation with Neutronic-Temperature Coupling in the Fuel Pellet of Light Water Reactor [J]. Annals of Nuclear Energy, 140(2020): 107297. doi: 10.1016/j.anucene.2019.107297.

(2019)

5. 王翔*, 何迅, 拉斐尔·马西安-胡安. 双流熔盐堆研究综述[J]. 核科学与工程, 2019(38)Suppl: 280-290. (X. Wang, X. He, R. Macian-Juan. Research Review of the Dual Fluid Reactor [J]. Nuclear Science and Engineering, 2019(38)Suppl: 280-290.)

4. X. Wang*, Q. Zhang, K. Zhuang, X. He, M. Seidl, R. Macian-Juan. Neutron Physics of the Liquid-Fuel Heat-Pipe Reactor Concept with Molten Salt Fuel - Static Calculations [J]. International Journal of Energy Research, 2019(43)14: 7852-7865. doi:10.1002/er.4642.

3. Q. Zhang*, X. Wang, Y. F. Zhang, X. M. Chi, L. Liang, K. Zhuang, C. Wang. Neutronic analysis for potential Accident Tolerant Fuel UO2-BeO in the light water reactor[J]. Annals of Nuclear Energy, 2019(127): 278-292. doi: 10.1016/j.anucene.2018.12.014.

2. X. Wang*, C. Y. Liu, R. Macian-Juan. Preliminary Hydraulic Analysis of the Distribution Zone in the DFR Concept[J]. Progress in Nuclear Energy, 2019(110): 364-373. doi: 10.1016/j.pnucene.2018.10.015.

(2018)

1. X. Wang*, Rafael Macian-Juan. Steady State Reactor Physics of the Dual Fluid Reactor Concept[J]. International Journal of Energy Research, 2018(42)14: i, 4313-4334. doi: 10.1002/er.4171.

会议（54）

(2023)
54. Qinyu Zhang, Chenrui Shang, Xiang Wang*. The Preliminary Approach of a Modelica-Based Single-Particle Accelerator Simulator [C]. ICONE30-1255, 30th International Conference on Nuclear Engineering (ICONE-2023), Kyoto, Japan, 2023.05.21-26.

53. Zhichao Zhang, Rafael Macian-Juan, Xiang Wang*. Numerical Analysis of the venturi Flowmeter in the Liquid Lead-bismuth Eutectic Circuit after Long-Term Operation [C]. International Congress on Advances in Nuclear Power Plants (ICAPP-2023), Gyeongju, Korea, 2023.04.23~27.

(2022)

52. Xuanang He, Dalin Zhang, Xiang Wang*. Visualized Numerical Analysis of FuSTAR Reactor Based on Modelica Language [C]. Pacific Basin Nuclear Conference (PBNC-2022), Chengdu, China, 2022.10.31-11.04.

51. Yaoqi Luo, Marcus Seidl, Xiang Wang*. Design and Verification of BNCT Beam Shaping Assembly Based on Genetic Algorithm [C]. Pacific Basin Nuclear Conference (PBNC-2022), Chengdu, China, 2022.10.31-11.04.

50. Shishuai Wang, Xiang Wang*. Simulation of Photon-counting Detector Based on OpenModelica [C]. Pacific Basin Nuclear Conference (PBNC-2022), Chengdu, China, 2022.10.31-11.04.

49. Yantao Luo, Xiang Wang*. The Thermo-hydraulics Calculation of Unfolding Process about the LOTUS Reactor [C]. Pacific Basin Nuclear Conference (PBNC-2022), Chengdu, China, 2022.10.31-11.04.

48. Xuesong Bai, Xiang Wang*. Physical Performance Study of Depletion Features for the Liquid-Fuel Heat-Pipe Reactor [C]. International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (NUTHOS-13), NUTHOS13-N13P024, Taichung, Taiwan (China), 2022.09.05-10.

47. 张傲, 王翔*. 基于Modelica语言的船舶核动力系统闭合回路建模仿真计算[C]. 中国核学会反应堆热工流体力学分会第二届学术年会暨中核核反应堆热工水力技术重点实验室2022年学术年会暨国家能源压水反应堆技术研发（实验）中心学术交流会. 哈尔滨, 中国, 2022.07.26-29. (Ao Zhang, Xiang Wang*. Closed Loop Modelling and Simulation of Marine Nuclear Power System Based on Modelica. The 2nd Annual Conference of the Reactor Thermo-hydrodynamics Branch of the China Nuclear Society, and the 2022 Academic Annual Conference of the Key Laboratory of Thermal Hydraulic Technology in Nuclear Reactors of CNNC, and the Academic Exchange Meeting of the National Energy R&D (Experimental) Center for PWR Technology, Harbin, China. 2022.07.26-29)

46. 余长江，王翔*. 基于Modelica语言的熔盐堆燃料流速物理分析[C]. 中国核学会反应堆热工流体力学分会第二届学术年会暨中核核反应堆热工水力技术重点实验室2022年学术年会暨国家能源压水反应堆技术研发（实验）中心学术交流会. 哈尔滨, 中国, 2022.07.26-29. (Changjiang Yu, Xiang Wang*. Physical Analysis of Fuel Velocity of the Molten Salt Reactor Using Modelica Language. The 2nd Annual Conference of the Reactor Thermo-hydrodynamics Branch of the China Nuclear Society, and the 2022 Academic Annual Conference of the Key Laboratory of Thermal Hydraulic Technology in Nuclear Reactors of CNNC, and the Academic Exchange Meeting of the National Energy R&D (Experimental) Center for PWR Technology, Harbin, China. 2022.07.26-29)

45. 罗耀琦, 马库斯·赛德, 王翔*. 基于遗传算法的BNCT束流整形组件优化设计[C]. 中国辐射防护学会2021/2022年学术年会暨21世纪初辐射防护论坛第19/20次会议. 青岛, 中国, 2022.08.16-20. (Yaoqi Luo, Marcus Seidl, Xiang Wang*. Optimization Design of BNCT Beam Shaping Assembly Based on Genetic Algorithm. The 2021/2022 Annual Conference of the Chinese Society for Radiation Protection and the 19th/20th Meeting of the Early 21st Century Radiation Protection Forum, Qingdao, China. 2022.08.16-20)

44. 杨旭辉, 马库斯·赛德, 王翔*. GEANT 4与MCNP应用于屏蔽材料积累因子的测量[C]. 中国辐射防护学会2021/2022年学术年会暨21世纪初辐射防护论坛第19/20次会议. 青岛, 中国, 2022.08.16-20. (Xuhui Yang, Marcus Seidl, Xiang Wang*. Feasibility Research on the Application of Equivalent Atomic Number Method in Calculation of Build-up Factor of Shielding Materials based on MC Codes. The 2021/2022 Annual Conference of the Chinese Society for Radiation Protection and the 19th/20th Meeting of the Early 21st Century Radiation Protection Forum, Qingdao, China. 2022.08.16-20)

43. Yuxuan Liang, Xiang Wang*. Preliminary Sensitivity and Uncertainty Analysis of Accident Tolerant Fuel in SMR[C]. ICONE29-92887, 29th International Conference on Nuclear Engineering (ICONE-2022), Shenzhen, China, 2022.08.08-12.

42. Xiang Tang, Xiang Wang*. Simulation of One-Dimensional Nuclear-Pumped Laser Generation System Based on Modelica Language[C]. ICONE29-92567, 29th International Conference on Nuclear Engineering (ICONE-2022), Shenzhen, China, 2022.08.08-12.

41. Hanyang Lyu, Xiang Wang*. Simulation of Plasma Magnetic Confinement System Based on Modelica Language: Starting with A Single Particle[C]. ICONE29-92564, 29th International Conference on Nuclear Engineering (ICONE-2022), Shenzhen, China, 2022.08.08-12.

40. Jie Liu, Tian Zhang, Xiang Wang*. Modelica Based Economic Analysis of Closed Nuclear Fuel Cycle[C]. ICONE29-91600, 29th International Conference on Nuclear Engineering (ICONE-2022), Shenzhen, China, 2022.08.08-12.

39. Ao Zhang, Xiang Wang*. Propulsion Control of Marine Nuclear Reactor by Hardware-In-The-Loop Simulation (HILS) [C]. ICONE29-91544, 29th International Conference on Nuclear Engineering (ICONE-2022), Shenzhen, China, 2022.08.08-12.

38. Heliang Wang, Xiang Wang*. Sensitivity Analysis of Small Modular Reactor mPower with ATHLET[C]. International Conference on Physics of Reactors (PHYSOR-2022), PHYSOR2022-37320, Pittsburgh, USA, 2022.05.15-20.

37. Yantao Luo, Xiang Wang*. Development of keff in the Unfolding Process of the LOTUS Reactor Design[C]. International Conference on Physics of Reactors (PHYSOR-2022), PHYSOR2022-37324, Pittsburgh, USA, 2022.05.15-20.

36. Loretta Boahemaa Manu, Xiang Wang*. Criticality Analysis of a Variant Model of a Spent Fuel Cask[C]. International Conference on Physics of Reactors (PHYSOR-2022), PHYSOR-37592, Pittsburgh, USA, 2022.05.15-20.

35. 罗彦滔, 张田, 王翔*. LOTUS堆的展开过程分析[C]. 全国新堆与研究堆学术报告交流会. 惠州, 中国, 2022.XX-XX. (Yantao Luo, Tian Zhang, Xiang Wang*. Unfolding Process Analysis of a LOTUS Reactor. National Academic Meeting of New Reactor and Research Reactor, Huizhou, China. 2022.05)

34. 李晓飞, 王翔*. 径向热管反应堆稳态物理分析与参数优化[C]. 全国新堆与研究堆学术报告交流会. 惠州, 中国, 2022.XX-XX. (Xiaofei Li, Xiang Wang*. Parameter Optimization and Steady-State Core Physics Analysis of Radially Arranged Heat-Pipe Reactor. National Academic Meeting of New Reactor and Research Reactor, Huizhou, China. 2022.05)

(2021)

33. 常昊, 王翔*. 基于肖特基型4H-SiC探测器的脉冲中子探测技术模拟研究[C]. 《中国核科学技术进展报告（第七卷）》, 1192.中国核学会年会, 烟台, 中国, 2021.10.19-22. (Hao Chang, Xiang Wang*. Simulation study on the detection of pulsed neutron based on Schottky 4H-SiC detector. Annual Meeting of the Chinese Nuclear Society, Yantai, China. 2021)

32. 刘嵩阳, 王翔*. 双流体熔盐堆单棒束热工水力与中子物理耦合计算[C]. 核动力院核反应堆系统设计重点实验室2021年学术年会, 成都, 中国, 2021.08.XX-XX. (Songyang Liu, Xiang Wang*. Neutronics and Thermal-hydraulic Coupling Calculation of the Single Tube Bundle in the Dual Fluid Reactor. Annual Meeting of the Key Laboratory of the Nuclear Reactor System, Nuclear Power Institute of China, Chengdu, China. 2021)

31. 贾茗涵, 王翔*. 基于Modelica的一维液态金属热管特性研究[C]. 核动力院核反应堆系统设计重点实验室2021年学术年会, 成都, 中国, 2021.08.XX-XX. (Minghan Jia, Xiang Wang*. Characteristic Study of a One-dimensional Liquid-Metal Heat-pipe based on Modelica. Annual Meeting of the Key Laboratory of the Nuclear Reactor System, Nuclear Power Institute of China, Chengdu, China. 2021)

30. 白雪松, 王翔*. 液态燃料热管反应堆增殖性能研究[C]. 核动力院核反应堆系统设计重点实验室2021年学术年会, 成都, 中国, 2021.08.XX-XX. (Xuesong Bai, Xiang Wang*. Breeder Characteristics of a Liquid-Fuel-Heat-Pipe Reactor. Annual Meeting of the Key Laboratory of the Nuclear Reactor System, Nuclear Power Institute of China, Chengdu, China. 2021)

29. Emir Hanic, Haris Lulic, Tarik Hadzovic, Xiang Wang*. Radon Leakage Simulation in Working Space with and without Ventilation[C]. International Congress on Advances in Nuclear Power Plants (ICAPP-2021), Abu Dhabi, UAE, 2021.10.16-20.

28. Xiang Tang, Hanyang Lyu, Rafael Macian-Juan, Xiang Wang*. Cooling System Simulation of the HELIMAK Device [C]. International Congress on Advances in Nuclear Power Plants (ICAPP-2021), Abu Dhabi, UAE, 2021.10.16-20.

27. Hanyang Lyu, Xiang Tang, Rafael Macian-Juan, Xiang Wang*. Electromagnetic Field Simulation of the HELIMAK Device [C]. International Congress on Advances in Nuclear Power Plants (ICAPP-2021), Abu Dhabi, UAE, 2021.10.16-20.

26. Yuxuan Liang, Qian Zhang, Xiang Wang*. Neutronic Analysis for Potential Accident Tolerant Fuel UO2-BeO in the Small Modular Reactor [C]. International Congress on Advances in Nuclear Power Plants (ICAPP-2021), Abu Dhabi, UAE, 2021.10.16-20.

25. Mingyue Wang, Qiang Yan, Xiang Wang*. An optimal design of fuel type for Single-pass Super-critical Water-Cooled Reactor Core [C]. International Congress on Advances in Nuclear Power Plants (ICAPP-2021), Abu Dhabi, UAE, 2021.10.16-20.

24. Songyang Liu, Xiang Wang*. Preliminary Neutron Physics Calculations of the LOTUS Reactor [C]. International Congress on Advances in Nuclear Power Plants (ICAPP-2021), Abu Dhabi, UAE, 2021.10.16-20.

23. Chaoyi Zhang, Chunyu Liu, Rafael Macian-Juan, Xiang Wang*. Preliminary Design Optimization of Venturi Flowmeter for Lead - based Loop [C]. International Congress on Advances in Nuclear Power Plants (ICAPP-2021), Abu Dhabi, UAE, 2021.10.16-20.

22. Runkai Chen, Qiang Yan, Xiang Wang*. Radiation Protection Design of Small Modular Dual Fluid Reactor Concept [C]. International Congress on Advances in Nuclear Power Plants (ICAPP-2021), Abu Dhabi, UAE, 2021.10.16-20.

21. Songyang Liu, Xiang Wang*. Neutron Physics Characterization & Optimization Analysis of the ACPR100 Small Modular Reactor [C]. International Conference on Nuclear Engineering (ICONE-2021), ICONE28-65689, Online, 2021.08.04-06. EI, doi: 10.1115/ICONE28-65689. Accession number: 20214311079095.

20. Songyang Liu, Xiang Wang*. Study of Physical Parameters Based on ACPR100 Reactor Core [C]. The 5th International Conference on Physics and Technology of Reactors and Applications (PHYTRA), Xi’an, China. 2021.05.09-12.

19. Xuesong Bai, Xiang Wang*. The Preliminary Depletion Analysis of the LFHPR [C]. The 5th International Conference on Physics and Technology of Reactors and Applications (PHYTRA), Xi’an, China. 2021.05.09-12.

(2020)

18. Yuxuan Liang, Xiang Wang*. Preliminary Neutronic analysis for the combination of U3Si2/Al-Si dispersed fuel and SiC in the small modular reactor [C]. The 18th Conference on Core Reactor Physics (CORPHY-2020), Xi’an, China, 2020.08.26-31. (梁宇轩, 王翔*. 基于SMR的U3Si2/Al-Si弥散燃料–SiC组合的初步中子学分析[C]. 第十八届反应堆数值计算与粒子输运学术会议暨2020年反应堆物理会议(CORPHY2020), 西安, 中国, 2020.08.26-31)

17. Runkai Chen, Gengzuo Liu, Qian Zhang, Xun He, Qingyu Wang*, Xiang Wang*. Comparable study of Monte Carlo programs based on smDFR [C]. The 18th Conference on Core Reactor Physics (CORPHY-2020), Xi’an, China, 2020.08.26-31. (陈润开, 刘耕佐, 张乾, 何迅, 王庆宇*, 王翔*. 基于smDFR的蒙卡程序对比计算分析[C]. 第十八届反应堆数值计算与粒子输运学术会议暨2020年反应堆物理会议(CORPHY2020), 西安, 中国, 2020.08.26-31)

16. Dongyu Xu, Qian Zhang*, Xiaomiao Chi, Yunfan Ma, Zhenyu Yang, Qiang Zhao, Xiang Wang. Control rod burn up correction mechanism [C]. The 18th Conference on Core Reactor Physics (CORPHY-2020), Xi’an, China, 2020.08.26-31. (徐东宇, 张乾, 池晓淼, 马云帆, 杨振宇, 赵强, 王翔. 控制棒燃耗修正方法[C]. 第十八届反应堆数值计算与粒子输运学术会议暨2020年反应堆物理会议(CORPHY2020), 西安, 中国, 2020.08.26-31)

(2019)

15. Liping HUANG, Zijing Liu, Xiang Wang*. Study on the Optimization of Assembly Design of Single-Pass Supercritical Water-Cooled Fast Reactor [C]. Proceedings of the 3rd Reactor Physics Asia Conference in 2019 (RPHA19), 2019.12.02-03, Osaka, Japan. KURNS-EKR-5, ISSN 2434-1088, Institute for Integrated Radiation and Nuclear Science, Kyoto University (2019).

14. 张超毅, 王翔*, 张乾, 何迅, 马库斯•赛德, 拉斐尔•马西安-胡安. 铅基回路文丘里流量计初步设计优化[C]. 第十六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2019年学术年会, 惠州, 中国, 2019.11.05-08. (Chaoyi Zhang, Xiang Wang*, Qian Zhang, Xun He, Marcus Seidl, Rafael Macian-Juan. Preliminary Design Optimization of Venturi Flowmeter for Lead - based Loop. 16th National Academic Meeting on the Reactor Thermal-hydraulics, Huizhou, China. 2019). doi: 10.26914/c.cnkihy.2019.047886

13. 王翔*, 张乾, 何迅, 马库斯•赛德, 拉斐尔•马西安. 液态金属燃料双流堆堆芯物理可行性初步分析[C]. 核动力院核反应堆系统设计重点实验室2019年学术年会, 成都, 中国, 2019.08.18-20. (Xiang Wang*, Qian Zhang, Xun He, Marcus Seidl, Rafael Macian. Preliminary Feasibility Analysis of a Liquid-Metal Fuel Dual Fluid Reactor Core. Annual Meeting of the Key Laboratory of the Nuclear Reactor System, Nuclear Power Institute of China, Chengdu, China. 2019)

12. 张晋超, 张乾, 王翔, 梁亮. 基于改进缺陷因子的弥散颗粒燃料均匀化方法[C]. 核动力院核反应堆系统设计重点实验室2019年学术年会, 成都, 中国, 2019. (Jinchao Zhang, Qian Zhang, Xiang Wang, Liang Liang. A homogenization method for the dispersed pellet fuel based on improved defect factor. Annual Meeting of the Key Laboratory of the Nuclear Reactor System, Nuclear Power Institute of China, Chengdu, China. 2019)

11. 余剑, 张乾, 王翔, 张晋超. 压水堆燃料棒中子学与燃料性能耦合燃耗计算研究[C].核动力院核反应堆系统设计重点实验室2019年学术年会, 成都, 中国, 2019. (Jian Yu, Qian Zhang, Xiang Wang, Jinchao Zhang. Computational study on fuel consumption coupled with fuel performance of PWR fuel rods. Annual Meeting of the Key Laboratory of the Nuclear Reactor System, Nuclear Power Institute of China, Chengdu, China. 2019)

10. 王翔*, 张乾, 何迅, 杜卓奇, 马库斯•赛德, 拉斐尔•马西安-胡安. 小型模块化双流熔盐铅基堆中子物理可行性静态分析[C]. 中国核学会船用核动力分会2019年学术年会, 成都, 中国, 2019. (Xiang Wang*, Qian Zhang, Xun He, Zhuoqi Du, Marcus Seidl, Rafael Macian. The Neutron Physical Feasibility of a Small Modular Dual Fluid Reactor. Annual Academic Meeting of the Marine Nuclear Power Branch of the Chinese Nuclear Society, Chengdu, China. 2019)

9. X. Wang*, Q. Zhang, X. He, Z. Q. Du, M. Seidl, R. Macian-Juan, K. Czerski, M. Dabrowski. Neutron physical feasibility of a small modular dual fluid reactor [C]. The proceedings of the International Conference on Nuclear Engineering (ICONE-2019), 2019.27 1229, Ibaraki, Japan, 2019. EI, doi: 10.1299/jsmeicone.2019.27.1229. Accession number: 20193507377977.

8. Q. Zhang, X. M. Chi, Y. F. Zhang, L. Liang, Q. Zhao, X. Wang, X. J. Wen. Neutronic Evaluation of the UO2-BeO Fuel Based on the Lattice Physics Calculation [C]. The proceedings of the International Conference on Nuclear Engineering (ICONE-2019), 2019.27 1264, Ibaraki, Japan, 2019. EI, doi: 10.1299/jsmeicone.2019.27.1264. Accession number: 20193507378003.

(2018)

7. X. Wang. Draining Time of the Dual Fluid Reactor [C]. 12th International Topical Meeting on Nuclear Reactor Thermal-hydraulics, Operation and Safety (NUTHOS-12), Qingdao, China, 2018.

6. X. Wang. Review of the Research of the DFR [C]. The 17th Conference on Core Reactor Physics (CORPHY-2018), Shenzhen, China, 2018. (王翔. 双流熔盐堆研究综述[C]. 第十七届反应堆数值计算和粒子输运学术会议暨2018年反应堆物理会议(CORPHY2018), 深圳, 中国, 2018.)

5. X. Wang*, C. Y. Liu, R. Macian-Juan. Dynamics and Stability Analysis of DFR Concept Using U-PU and TRU Fuel Salts [C]. International Congress on Advances in Nuclear Power Plants (ICAPP-2018), Charlotte, USA, 2018. Proceedings of the 2018 International Congress on Advances in Nuclear Power Plants, ICAPP 2018, 460-468, 2018. EI, Accession Number: 20182905580931

(2017)

4. X. Wang*, R. Macian-Juan. Comparative Study of Basic Reactor Physics of the DFR Concept using UPu & TRU Fuel Salts [C]. International Conference on Nuclear Engineering (ICONE-2017), Shanghai, China, 2017. SCI, doi: 10.1115/ICONE25-66035. EI, Accession number: 20174404358709.

3. X. Wang*, R. Macian-Juan. Comparative Study of Thermal-hydraulic Behavior of the DFR using UPu & TRU Fuel Salts [C]. International Conference on Nuclear Engineering (ICONE-2017), Shanghai, China, 2017. SCI, doi: 10.1115/ICONE25-66061. EI, Accession number: 20174404358762.

2. X. Wang*, C. Y. Liu, R. Macian-Juan. Preliminary Hydraulic Analysis of the Distribution Zone in the DFR Concept [C]. International Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-2017), Xi’an, China, 2017.

(2015)

1. X. Wang*, R. Macian-Juan, M. Seidl. Preliminary Analysis of Basic Reactor Physics of the Dual Fluid Reactor Concept [C]. International Congress on Advances in Nuclear Power Plants (ICAPP-2015), Nice, France, 2015.

荣誉

奖励

Personal Information

Introduction：
Education Background :
Professional Experience :
Qualifications and Skills :
Academic Positions and Titles :

Research

Research Fields：
Projects：
Honors and Awards、Academic Activities：

Teaching

Admission:
Courses:
Practical Teaching：

Publications

Books:
Journal and Conferences:
Patents:
Software Copyrights:	"

研究团队

先进反应堆多物理耦合分析 (Multi-physical Coupling Analysis of Advanced Reactor)

基于加速器与辐射的核技术应用 (Accelerator and Radiation based Nuclear Technology Application)

低碳能源发展应用研究 (Research of Development and Application of Low-Carbon Energy)

硕士研究生培养

	入学年份	姓名	论文题目	毕业去向
1	2019	陈润开	基于遗传算法的小型熔盐铅基堆堆芯优化与一次屏蔽设计	杭州嘉辐科技
2	2019	梁宇轩	小型压水堆事故容错燃料中子学与不确定性分析	核动力研究设计院
3	2019	刘嵩阳	基于Serpent和OpenFOAM的smDFR堆芯核热耦合研究	华能核能技术研究院
4	2019	王明月	DFR与S-CO2布雷顿循环耦合核动力系统瞬态数值模拟分析	GK核技术支持中心
5	2019	张超毅	小型双流体熔盐堆堆芯流体多物理特性分析	中核核电运行研究院
6	2020	罗彦滔
7	2020	罗耀琦
8	2020	余长江
9	2020	杨旭辉
10	2021	程德琪
11	2021	段林
12	2021	焦宇珍
13	2021	杨晟傑
14	2021	王博文
15	2022	李晓飞
16	2022	赵泽林
17	2022	张傲

ENGLISH

INTRODUCTION
Dr.-Ing., Associate Professor, Master's Supervisor.
He has led and participated more than 10 national and provincial projects, published 1 academic monograph, over 40 journal and conference papers, 4 authorized patents and software copyrights. He is also the reviewer of International Journal of Energy Research and Nuclear Science and Techniques as well as other journals.

RESEARCH
Multi-physics Nuclear Reactor Technology including:
1. Reactor Core Design
2. Neutron Physics Calculation
3. Thermal-hydraulic Simulation
4. Radiation Shielding & Design
5. System Performance and Safety Analysis
6. Nuclear Fuel Cycling & Comprehensive Application

CAREER & PRACTICE

2017.11～Now Harbin Engineering University, College of Nuclear Science and Technology, Associated Professor

2016.03～2017.09 Technische Universität München (Germany), Lehrstuhl für Nukleartechnik, Wiss. Mitarbeiter

2011.10～2012.10 Gesellschaft für Anlagen- und Reaktorsicherheit (GRS, Germany), Werkstudent

2011.07～2011.09 Technische Universität München (Germany), Lehrstuhl für Nukleartechnik, Wiss. Hilfskraft

2010.06～2011.06 Technische Universität München (Germany), Lehrstuhl für Nukleartechnik, Stud. Hilfskraft

2008.02～2008.12 Tsinghua University, Department of Engineering Physics, SRT Student
2006.09～2008.02 Tsinghua University, Department of Engineering Physics, SRT Student

EDUCATION

2013.01-2017.07 Technische Universität München (Germany), Nukleartechnik, Dr.-Ing.

2010.09-2011.04 Institut National des Sciences et Techniques Nucléaires (France), Exchange

2010.03-2012.12 Technische Universität München (Germany), Nukleartechnik, M.Sc.

2009.03-2010.03 Technische Universität Darmstadt (Germany), Physics

2004.09-2008.08 Tsinghua University, Engineering Physics, B.-Eng.

王翔