Design and Verification of Reactor Power Control Based on Stepped Dynamic Matrix Controller

Table 1

Data for simulation of PWR plant [26].

Parameters	Values	Explanations
n0	0.5 m^−3	Equilibrium density of neutron
Gr	0.0290	Value of control rod per unit length
P0	2500 MW	Rated power of reactor core
	(n0 − 4.24) × 10^−5°C^−1	Temperature coefficient of reactivity of fuel
λ	0.15 s^−1	Decay constant of the delayed neutron
	(160n0/9 + 54) MW·s·°C^−1	Heat capacity of coolant
	0.006019	Total fraction of effective delayed neutron
Ω	(5n0/3 + 4.93) MW·s·°C^−1	Heat transfer coefficient between the fuel and the coolant
ff	0.92	Fraction of fuel power
M	(28n0 + 74) MW·s·°C^−1	Heat capacity per unit mass of flow
	0.00002 s	Generation time of neutron
	(−4 n0−17.3) × 10^−5°C^−1	Temperature coefficient of reactivity of coolant
	2.63 MW·s·°C^−1	Heat capacity of fuel