| 摘要 |
FIELD: nuclear power engineering. ^ SUBSTANCE: proposed method for evaluating steam reactance factor at nuclear power stations using type RBMK reactors makes use of control and protection system, reactor heat power varying facilities, and feedwater level gages for drum-type separators incorporating automatic or manual control drives. With control rods inserted in reactor core, variations in reactor heat power, steam pressure in drum-type steam separator, and feedwater flow over reactor core sections are recorded. In the process reactance factor is calculated by solving set of reactance-balance least-squares equations compiled for each measurement while varying feedwater flow and moving control rods. ^ EFFECT: reduced amplitude of feedwater flow disturbances, enhanced safety and operating efficiency of nuclear power stations. ^ 1 cl, 4 dwg |
