Optimal Tracking Control for a Discrete Time Nonlinear Nuclear Power System

Table 1

Nomenclature.

Nomenclature
	Reactivity worth of the control rod bank
	Nominal core power (MW)
	Mean neutron lifetime (s)
	The total fraction of effective the ith group of delayed neutrons
	The heat transfer coefficient between fuel and coolant (°C)
M	Heat capacity of mass flux of coolant ( °C)
	The reactivity coefficient of coolant temperature
	The reactivity coefficient of fuel temperature.
	Heat capacity of coolant (°C)
	Heat capacity of fuel (°C)
	Equivalent single-group delayed neutron precursor nuclear decay constant
	Core reactivity
	Average inlet temperature of coolant (°C)
	Initial equilibrium inlet temperature of coolant (°C)
	Initial equilibrium outlet temperature of coolant (°C).
	Initial equilibrium fuel temperature (°C).