Coordinated control system design of HTR-PM plant

The modular high temperature reactor (MHTGR), which adopts helium as coolant and graphite as moderator and structural material, has inherent nuclear safety. Based upon multi-modular scheme, i.e. the outlet steam flows of multiple nuclear steam supply system (NSSS) modules are combined together to drive a single turbine, the inherent safety feature can be applicable to the plants at any desired power ratings. However, the power control method of classical single-modular nuclear power plants (NPPs) cannot be applied directly. The coordinated control system design of HTR-PM plant, which is the first multi-modular nuclear plant being constructed in the world, is proposed in this paper. Then, the control system design is verified based on the full-scale simulator of HTR-PM plant, and the simulation results in the cases of power ramp down and high pressure heater bypass are given, which show the feasibility of control system design and the acceptable transient performance of the closed-loop.

[1]  Zhe Dong,et al.  Saturated Output Feedback Dissipation Steam Temperature Control for the OTSG of MHTGRs , 2011, IEEE Transactions on Nuclear Science.

[2]  Zhe Dong,et al.  Module Coordination Control of MHTGR-Based Multi-Modular Nuclear Plants , 2016, IEEE Transactions on Nuclear Science.

[3]  Zhe Dong.  Model-Free Coordinated Control for MHTGR-Based Nuclear Steam Supply Systems , 2016 .

[4]  Zuoyi Zhang,et al.  Economic potential of modular reactor nuclear power plants based on the Chinese HTR-PM project , 2007 .

[5]  Yujie Dong,et al.  Current status and technical description of Chinese 2 × 250 MWth HTR-PM demonstration plant , 2009 .

[6]  Yuanle Ma,et al.  The engineering simulation system for HTR-PM , 2014 .

[7]  Zhe Dong.  Dissipation analysis and adaptive control of fluid networks , 2015, 2015 American Control Conference (ACC).

[8]  Zongxin Wu,et al.  The design features of the HTR-10 , 2002 .

[9]  G. R. Ansarifar,et al.  Sliding mode control design for a PWR nuclear reactor using sliding mode observer during load following operation , 2015 .

[10]  Zhe Dong,et al.  Coordination Control of SMR-Based NSSS Modules Integrated by Feedwater Distribution , 2016, IEEE Transactions on Nuclear Science.

[11]  Man Gyun Na,et al.  Design of a fuzzy model predictive power controller for pressurized water reactors , 2006, IEEE Transactions on Nuclear Science.

[12]  Hong Wang,et al.  The Shandong Shidao Bay 200 MW e High-Temperature Gas-Cooled Reactor Pebble-Bed Module (HTR-PM) Demonstration Power Plant: An Engineering and Technological Innovation , 2016 .

[13]  G. H. Lohnert,et al.  Technical design features and essentiaL safety-related properties of the HTR-module , 1990 .

[14]  K.Y. Lee,et al.  Fuzzy-adapted recursive sliding-mode controller design for a nuclear power plant control , 2004, IEEE Transactions on Nuclear Science.

[15]  Kwang Y. Lee,et al.  State Feedback Assisted Classical Control: An Incremental Approach to Control Modernization of Existing and Future Nuclear Reactors and Power Plants , 1990 .

[16]  Yuri B. Shtessel,et al.  Sliding mode control of the space nuclear reactor system , 1998 .

[17]  Yoon Joon Lee,et al.  Design of a fuzzy model predictive power controller for pressurized water reactors , 2006 .

[18]  Zhe Dong,et al.  Model-Free Power-Level Control of MHTGRs Against Input Saturation and Dead-Zone , 2015, IEEE Transactions on Nuclear Science.