极致安全小型堆

阶段性工作

开展了用于小型核反应堆的螺旋管直流蒸汽发生器的设计、计算与三维CFD仿真工作。并开发了用于小型堆螺旋管式直流蒸汽发生器的专用计算程序。
开展了小型极致安全核反应堆的概念设计、堆芯计算和一回路热工水力计算。
针对高温气冷堆开展了安全分析与评估。
对核能的综合利用开展了研究,研究核能与生物质能的耦合方法。

相关论文

  • H. Ding, Y. Zhang, K. Ye, and G. Hong, “Development of a model for thermal-hydraulic analysis of helically coiled tube once-through steam generator based on Modelica,” Ann. Nucl. Energy, p. 107069, Sep. 2019.
  • Z. Li, Y. Zhang, Q, Gao, et al., “Safety analysis of a small modular reactor using fully ceramic micro-encapsulated fuel,” Prog. Nucl. Energy, vol. 113, pp. 74–83, May 2019.
  • K. Ye, Y. Zhang*, X. Sheng, N. Li, Y. Yang, and Y. Chen, “Numerical analysis of the flow behavior in a helically coiled once through steam generator,” Nucl. Eng. Des., vol. 330, pp. 187–198, Apr. 2018.
  • Y. Zhang, J. Buongiorno, M. Golay, N. Todreas, Safety Analysis of a 300-MW(electric) Offshore Floating Nuclear Power Plant in Marine Environment, Nucl. Tech., 203:2 (2018), 129-145, DOI: 10.1080/00295450.2018.1433935
  • J. Huang, N. Li, Y. Zhang, J. Lin, Q. Guo, The excess reactivity management in small pressurized water reactor utilizing fully ceramic microencapsulated fuel, Prog. Nucl. Energy. 101 (2017) 251–259. doi:10.1016/j.pnucene.2017.08.005.
  • Y. Zhang, D. Wang, J. Lin, J. Hao, Development of a Computer Code for Thermal-hydraulic Design and Analysis of Helically Coiled Tube Once-through Steam Generator, Nuclear Engineering and Technology, 2017
  • J. Huang, N. Li, Y. Zhang, Q. Guo, J. Zhang, The safety analysis of a small pressurized water reactor utilizing fully ceramic microencapsulated fuel, Nucl. Eng. Des. 320 (2017) 250–257.