Research Article
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 |
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