2541
当前位置: 首页   >  成果及论文
成果及论文

期刊(14)

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 buildup factor based on backpropagation neural network [J]. Expert Systems with Applications 177(115004), 2021. DOI: 10.1016/j.eswa.2021.115004. 

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, online, 2020.07. 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.

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. Seidld, 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, SCI., IF: 3.343.

3. Qian Zhang*, Xiang Wang, Yunfei Zhang, Xiaomiao Chi, Liang Liang, Kun Zhuang, Chao 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: https://doi.org/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.

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(32)

32. 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. 

31. 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. 

30. 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. 

29. 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. 

28. 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. 

27. 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. 

26. 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. 

25. 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. 

24. 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. 

23. 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. 

22. 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. 

21. 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. 

20. 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. 

19. 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. 

18. 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. 2021.05.09-1222.   

17. 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. (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),陕西西安,2020)

16.  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. (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),陕西西安,2020)

15. Liping HUANG, Zijing LIU*, Xiang WANG*, Study on the Optimization of Assembly Design of Single-Pass Supercritical Water-Cooled Fast Reactor [C]. Reactor Physics Asia 2019 (RPHA19) Conference, Osaka, Japan, 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.

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. 

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.

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.

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.

9. 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 Phyisics Calculation [C]. International Conference on Nuclear Engineering (ICONE-2019), Ibaraki, Japan, 2019.

8. X. Wang*, Q. Zhang, X. He, Z.Q. Du, M. Seidl, R. Macian-Juan, K. Czerski, M. Dabrovski, Neutron physical feasibility of small modular design of Dual Fluid Reactor [C], International Conference on Nuclear Engineering (ICONE-2019), Ibaraki, Japan, 2019.

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

6. 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.

4. 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.

3. X. Wang*, R. Macian-Juan, Comparative Study of Basic Reactor Physics of DFR using UPu & TRU Fuel Salts [C], International Conference on Nuclear Engineering (ICONE-2017), Shanghai, China, 2017.

2. X. Wang*, R. Macian-Juan, Comparative Study of Thermal-hydraulic Behavior of DFR using UPu & TRU Fuel Salts [C], International Conference on Nuclear Engineering (ICONE-2017), Shanghai, China, 2017.

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.