Construction and Analysis of a Dynamic Model for a Canadian Direct-Cycle SCWR for Control System Studies

In this paper, a dynamic model of the Canadian supercritical water-cooled reactor (SCWR) is developed to examine its dynamics for potential control system design and analysis. The model development is based on fundamental mass, energy, and momentum conservation equations of major components within the Canadian SCWR operating at supercritical condition. A full set of nonlinear dynamic equations is first derived, from which linearized models are obtained. The linearized models are validated against the full-order nonlinear models in both time domain and frequency domain. The open-loop dynamic characteristics of the Canadian SCWR are investigated through extensive simulations. Steady-state and dynamic couplings among different inputs and outputs are examined using relative gain array and Nyquist plots, and adequate input-output pairings are identified. Cross-coupling at different operating conditions is also evaluated to illustrate the nonlinear behaviors of the system. The developed dynamic model provides a necessary platform for systematic investigation in the control system design and analysis of the Canadian SCWR.

[1]  Sirish L. Shah,et al.  Interaction analysis in multivariable control systems , 1986 .

[2]  S. Koshizuka,et al.  Control of a Fast Reactor Cooled by Supercritical Light Water , 1998 .

[3]  R. D. Paranjape,et al.  Modeling and control of a supercritical coal fired boiler , 1996 .

[4]  Peiwei Sun,et al.  Construction of dynamic model of CANDU-SCWR using moving boundary method , 2011 .

[5]  C. K. Chow,et al.  CONCEPTUAL FUEL CHANNEL DESIGNS FOR CANDU-SCWR , 2008 .

[6]  Y. Oka,et al.  Improvements of Feedwater Controller for the Super Fast Reactor , 2010 .

[7]  S. Koshizuka,et al.  Control of a High Temperature Supercritical Pressure Light Water Cooled and Moderated Reactor with Water Rods , 2003 .

[8]  H. S. Cheng,et al.  Analytical modeling techniques for efficient heat transfer simulation in nuclear power plant transients , 1985 .

[9]  Xiaojin Huang,et al.  A lumped parameter dynamic model of the helical coiled once-through steam generator with movable boundaries , 2008 .

[10]  D. Struwe,et al.  High performance light water reactor , 2003 .

[11]  T. Schulenberg,et al.  Heat transfer at supercritical pressures. Literature review and application to an HPLWR , 2001 .

[12]  T. Fujii,et al.  Forced convective heat transfer to supercritical water flowing in tubes , 1972 .

[13]  Hujun Ling,et al.  Generalized predictive control algorithm applied to thermal power units based on PID neural network , 2010, 2010 2nd International Conference on Advanced Computer Control.

[14]  Tosio Kato.  Perturbation theory for linear operators , 1966 .

[15]  S. Koshizuka,et al.  Supercritical-pressure, Once-through Cycle Light Water Cooled Reactor Concept , 2001 .

[16]  E. Bristol.  On a new measure of interaction for multivariable process control , 1966 .