METHOD FOR AUTOMATIC CONTROL OF WATER MODERATED WATER COOLED REACTOR PLANT POWER Russian patent published in 2006 - IPC G21D3/08 G21D3/10 G21D3/12 

FIELD: nuclear power engineering; automatic power control of water moderated water cooled reactor plants.

SUBSTANCE: proposed method for on-load control of VVER reactor plant power with electric load varied between 10 and 102% of reactor rated power involves following operations: evaluation of rate of turbine power variation as result of turbine power signal conversion in transient component with transfer function W(P) = K₄ · P/(T₄ · P+ 1), where P is Laplace operator; K₄ is factor of probable value from 0 to 100; T₄ is time constant of probable value from 0 to 100, this being followed by selection of desired operation; or movement of controls upward for raising turbine power control, following condition being satisfied: [(P_dsrd - P_steam) · K₁ + (N_t - N_r) + K₅] > 0, where P_dsrd is desired steam pressure, Pa; P_steam is steam pressure, Pa; K₁ is factor of probable value from 0 to 1; N_t is turbine power, %; N_r is reactor power, %; K₅ is factor of probable value from 0 to 100; or movement of controls in case absolute difference in reactor and turbine power is higher by more than K₆ and turbine power does not increase assuming that condition |N_t - N_r| ≥ K₆ is satisfied, where K₆ is factor of probable value from 0 to 100. Direction in which controls are moved is determined by sign of N_t - N_r difference or else by that of P_dsrd - P_steam difference when deviation of reactor power from turbine power is between -K₆ and +K₆ in absence of turbine power increase, movement time of controls being determined assuming that condition (P_dsrd - P_steam) -K₂ · (1 - exp(-t/T₂)) · (P_dsrd - P_steam)/ |P_dsrd - P_steam| ≥ - Δdz is satisfied, where t is time; K₂ is factor of probable value from 0 to 100; T₂ is time constant of probable value between 0 and 10⁶; Δdz, is dead zone of three-position relay component function of probable value between 0 and 10⁶; interval time between steps of controls is found assuming that condition (P_dsrd - P_steam) - K₃ · (1 - exp(-t/T₃)) · (P_dsrd - P_steam)/ |P_dsrd - P_steam| ≤ - Δrz is satisfied, where t is time; K₃ is factor of probable value from 0 to 100; T₃ is time constant of probable value between 0 and 10⁶; Δrz, is reset zone of three-position relay component function of probable value between 0 and 10⁶.

EFFECT: improved operating conditions of reactor core fuel elements due to using reactor self-control abilities and minimized movement of control and protection system elements.

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