Pressurizer dynamic model and emulated programmable logic controllers for nuclear power plants cybersecurity investigations

Abstract This work demonstrates the functionality of the pressurizer using a fast-running three regions, non-equilibrium model and control programs of emulated PLCs. The state variables from an integrated model of primary loop in a representative PWR plant are communicated to the pressurizer’s emulated PLCs using a synchronized data transfer function. In turn, the PLCs communicate back instructions to the pressurizer model to adjust the pressure and water level to remain within preprogramed setpoints. Pressurizer model simultaneously solves the coupled mass and energy conservation equations in the saturated vapor and saturated and subcooled liquid regions using fixed step solver. Results demonstrate the response of the pressurizer model linked to an emulated pressure and water level PLCs in a simulated transient involving surge-in and surge-out events. The 50 ms response delay time for the emulated PLCs insignificantly affects operation and predictions of the pressurizer model.

[1]  Mohamed S. El-Genk,et al.  Selection and Validation of Fast and Synchronous Interface to the Controller of a Space Nuclear Reactor Power System , 2020 .

[2]  Yang Xue,et al.  Research on Pressurizer Water Level Control of Nuclear Reactor Based on CMAC and PID Controller , 2009, 2009 International Conference on Artificial Intelligence and Computational Intelligence.

[3]  Abdallah M. Abdallah,et al.  Pressurizer transients dynamic model , 1982 .

[4]  S. G. Margolis,et al.  PRESSURIZER PERFORMANCE DURING LOSS-OF-LOAD TESTS AT SHIPPINGPORT: ANALYSIS AND TEST. , 1968 .

[5]  Hee Cheon No,et al.  A Nonequilibrium Three-Region Model for Transient Analysis of Pressurized Water Reactor Pressurizer , 1986 .

[6]  Mauro Vitor de Oliveira,et al.  Application of artificial intelligence techniques in modeling and control of a nuclear power plant pressurizer system , 2013 .

[7]  Jin Jiang,et al.  A Hardware-in-the-Loop Simulation Platform for the Verification and Validation of Safety Control Systems , 2011, IEEE Transactions on Nuclear Science.

[8]  Thelma Virginia Rodrigues,et al.  OpenPLC: An open source alternative to automation , 2014, IEEE Global Humanitarian Technology Conference (GHTC 2014).

[9]  Amir N. Nahavandi,et al.  An improved pressurizer model with bubble rise and condensate drop dynamics , 1970 .

[10]  Fuyu Zhao,et al.  Multi-objective optimization of control parameters for a pressurized water reactor pressurizer using a genetic algorithm , 2019, Annals of Nuclear Energy.

[12]  H. Kretzschmar,et al.  The IAPWS Industrial Formulation 1997 for the Thermodynamic Properties of Water and Steam , 2000 .

[13]  Fuyu Zhao,et al.  Mathematical modeling of a pressurizer in a pressurized water reactor for control design , 2019, Applied Mathematical Modelling.

[14]  Sang-Nyung Kim An experimental and analytical model of a PWR pressurizer during transients , 1984 .

[15]  Luigi Colombo,et al.  A non-equilibrium control oriented model for the pressurizer dynamics , 2018, Progress in Nuclear Energy.

[16]  Yi Li,et al.  Development of an improved non-equilibrium multi-region model for pressurized water reactor pressurizer , 2019, Annals of Nuclear Energy.

[17]  V. J. Galan,et al.  POWER TRAIN: general hybrid simulation for reactor coolant and secondary system transient response , 1973 .

[18]  Jiashuang Wan,et al.  Development of a simulation platform for dynamic simulation and control studies of AP1000 nuclear steam supply system , 2015 .

[19]  Hossam A. Gabbar,et al.  Fuzzy logic control for improved pressurizer systems in nuclear power plants , 2014 .