教育背景

2001年9月~2006年7月哈尔滨工程大学控制理论与控制工程专业学习，2003年获工学硕士学位、2006年获工学博士学位

1997年9月~2001年7月哈尔滨工程大学核工程专业学习，2001年获工学学士学位

工作履历

2015年12月 - 至今，清华大学核能与新能源技术研究院，副研究员

2008年11月 - 2015年12月，清华大学核能与新能源技术研究院，助理研究员

2006年12月 - 2008年11月，清华大学汽车工程系，博士后

研究领域

从事核能科学与工程专业工作，主要研究领域为：核安全级数字化仪控系统/设备设计及工程实现、高可靠性安全软件设计和V&V（验证与确认）、系统仿真建模、动态可靠性建模与分析等。

学术成果

[1] Canxing Huang, Huasheng Xiong, Zhe Dong, Boyuan Li, Shuqiao Zhou. A coordinated control strategy for NHR200-II under load rejection condition[C]. Proceedings of 2024 31st International Conference on Nuclear Engineering, ICONE 2024, Volume 3, 2024.

[2] Boyuan Li, Duo Li, Jianghai Li, Chao Guo, Huasheng Xiong, Shuqiao Zhou, Xiaojin Huang. Quantifying Software Safety in Nuclear Power Plants: A Framework for Requirements Phase Assessment[C]. Proceedings of 2024 31st International Conference on Nuclear Engineering, ICONE 2024, Volume 10, 2024.

[3] Huang, Canxing; Xiong, Huasheng; Feng, Junting. Investigation of model-based anomaly detection method for the full-power natural circulation small modular reactor NHR200-II. Proceedings of 2022 29th International Conference on Nuclear Engineering, ICONE 2022, Virtual, Online, August 8-12, 2022.

[4] Zhang, Haojing; Xiong, Huasheng; Guo, Chao; Li, Duo; Huang, Xiaojin. Effect analysis of power supply topology on the reliability of the reactor protection system. Proceedings of 2021 28th International Conference on Nuclear Engineering, ICONE 2021, Virtual, Online, August 4-6, 2021.

[5] 曹枭虓，熊华胜，郭超，张皓景，李铎，黄晓津. 反应堆保护系统动态可靠性建模与分析. 自动化仪表. 2019, 40（06）.

[6] Cao, Xiaoxiao; Xiong, Huasheng; Guo, Chao; Li, Duo; Zhang, Haojing; Huang, Xiaojin. Petri Net Based Reliability Modeling of Reactor Protection System Considering Periodic Surveillance Testing. Proceedings of the 27th International Conference on Nuclear Engineering, ICONE 2019, Tsukuba, Ibaraki, Japan, May 19 – 24, 2019.

[7] Cao, Xiaoxiao; Guo, Chao; Xiong, Huasheng; Zhang, Haojing; Li, Duo; Huang, Xiaojin. A Preventive Maintenance Model with Periodic and Random Inspection Policy for a Three-Stage Failure Process. Proceedings of the 2018 3rd International Conference on System Reliability and Safety, ICSRS 2018, Nov. 24-26, 2018, Barcelona, Spain.

[8] Guo Chao, Xiong Huasheng, Huang Xiaojin, Li Duo. Design and Development Framework of Safety-Critical Software in HTR-PM. Science and Technology of Nuclear Installations, volume 2017.

[9] Guo Chao, Xiong Huasheng, Li Duo, Zhou, Shuqiao. Testing and reliability modelling of safety software for digital reactor protection system of HTR-PM. Proceedings of the 24th International Conference on Nuclear Engineering, ICONE24, June 26-30, 2016, Charlotte, NC, United states.

[10] 熊华胜，李铎. 基于Unscented卡尔曼滤波器的反应堆周期计算算法研究. 原子能科学与技术. 2014,48（10）：102-105页

[11] 熊华胜，郭超，李铎等.一种通信协议转换方法、装置及系统:ZL201410345720.1,2017.04.05.

[12] 熊华胜，李铎，黄晓津等.一种保护逻辑仿真装置和使用其的动态验证系统:ZL201410360234.7,2017.02.06.

[13] 李铎，熊华胜，乔宁等.裂变室输出信号的数字化处理系统及方法:ZL201110294857.5,2014.03.12.

熊华胜，李铎，黄晓津等.高温气冷堆数字化保护系统的集成测试方法及系统:ZL201110112335.9,2014.01.22.