2011-2014 德国卡尔斯鲁厄理工学院 先进核能所 博士
2008-2011 上海交通大学 核能科学与工程 硕士
2004-2008 上海交通大学 核科学与核技术 学士

2020 ― 今 上海交通大学hga010网页登录 核能科学与工程学院 副研究员
2015 ― 2019 上海交通大学hga010网页登录 核能科学与工程学院 讲师

先进反应堆研发
多尺度多物理场耦合
反应堆热工水力

纵向科研项目：
2018-2020，国家自然科学基金青年项目，液滴撞击高温表面的关键换热现象及模型研究，负责人
2019-2020，装发预研，XXXX，负责人
2019-2020，装发预研，XXXX，负责人
2019-2020，中国原子能科学研究院，液体悬浮式非能动停堆组件运动过程数值模拟程序开发与验证，负责人
2019-2020, 国家重大专项外协，超高温热工与事故分析软件验证，负责人
2017-2020，上海市自然科学基金，严重事故下沸腾现象对气溶胶释放影响的机理研究，负责人
2017-2018，国防重点实验室基金，XXXX，负责人

横向科研项目：
2018-2020, 中国原子能科学研究院, 粉末瞬态事故物理热工耦合分析研发, 负责人
2018-2019，国家电投集团科学技术研究院有限公司，两相临界流、相向流动限制模型开发测试, 负责人
2018-2019，国家电投集团科学技术研究院有限公司，COSINE安全壳熔池与氢气模型改进及测试验证, 负责人
2018-2018，中国原子能科学研究院，核热推进堆芯热工计算分析，负责人
2017-2019，中国原子能科学研究院，基于MOX堆芯的中国实验快堆堵流事故及钠火事故校核计算，负责人
2015-2015，中广核，STEP-14燃料组件5×5棒束电磁力计算，负责人

[SCI]
1. Guan, C., Chai, X., Zhang, T., Liu, X., & He, H. (2024). Mass and efficiency optimization of a He-Xe Brayton cycle for mobile, land-based nuclear microreactors. Energy Conversion and Management, 301, 118011.
2. Chai X, Liu X, Guan C, et al. Investigation of reactivity control strategies for a micro-transportable gas-cooled thermal reactor[J]. Nuclear Engineering and Design, 2024, 416: 112758.
3. Deng, JL., Wang, TS., Zhu, EP. et al. Dynamic evaluation of a scaled-down heat pipe-cooled system during start-up/shut-down processes using a hardware-in-the-loop test approach. NUCL SCI TECH 34, 177 (2023).
4. Wang T S, Chai X, Guan C R, et al. Numerical and theoretical investigations of heat transfer characteristics in helium–xenon cooled microreactor core[J]. Nuclear Science and Techniques, 2023, 34(11): 1-19.
5. Zhu E, Li T, Xiong J, et al. A super-real-time three-dimension computing method of digital twins in space nuclear power[J]. Computer Methods in Applied Mechanics and Engineering, 2023, 417: 116444.
6. Deng, J., Wang, T., Liu, X., Zhang, T., He, H., & Chai, X. (2023). Experimental study on transient heat transfer performance of high temperature heat pipe under temperature feedback heating mode for micro nuclear reactor applications. Applied Thermal Engineering, 230, 120826.
7. Li, W., Xie, Q., Pan, Q., Zhang, T., Chai, X., & Liu, X. (2023). A multi-region algorithm for N-TH coupling calculation and its application to nuclear thermal propulsion reactor. Annals of Nuclear Energy, 184, 109696.
8. Deng J, Liu X, Guan C, et al. Conceptual design and its optimization of an air-cooled nuclear reactor for aircraft propulsion considering both thermal and neutronic performance[J]. Annals of Nuclear Energy, 2023, 181: 109591.
9. Zhu E, Wang Z, Ma J, et al. Transient multiphysics characteristics of a space thermionic reactor based on a coupling analysis[J]. Nuclear Engineering and Design, 2023, 401: 112064.
10. Chai X, Guan C, Deng J, et al. Preliminary conceptual design of a moderated micro nuclear reactor core cooled by heat pipe[J]. Annals of Nuclear Energy, 2022, 179: 109399.
11. LI W, GUAN C, SONG H, et al. Numerical investigation of heat transfer characteristics of moderator assembly employed in a low-enriched uranium nuclear thermal propulsion reactor [J]. Frontiers in Energy Research, 2022, 10
12. Deng, J., Zeng, W., Wang, J., Ding, S., & Chai, X. (2022). Coupled neutronics and thermal-hydraulics transient simulation of a gas-cooled reactor in the aircraft nuclear propulsion system. Nuclear Engineering and Design, 389, 111674.
13. Guan, C., Chai, X., Zhang, T., & Liu, X. (2022). Preliminary lightweight core design analysis of a micro‐transportable gas‐cooled thermal reactor. International Journal of Energy Research, 46(12), 17416-17428.
14. Guan, C., Chai, X., Zhang, T., & Liu, X. (2022). Transient coupling analysis of loss-of-coolant accidents in HTR-PM based on CFD approaches. Annals of Nuclear Energy, 173, 109097.

课程名称：工程学导论 授课对象：本科生 学时数： 48 学分： 3
课程名称：复杂系统的设计与实践 授课对象：研究生 学时数：64 学分：4

2021 上海市青年科技启明星