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
| Title | Year | Author | Number |
|---|---|---|---|
| METHOD OF DETERMINING STEAM COEFFICIENT OF REACTIVITY | 2011 |
|
RU2465660C1 |
| METHOD FOR EVALUATING STEAM VOID COEFFICIENT OF REACTIVITY | 2006 |
|
RU2315377C1 |
| METHOD FOR DETERMINING STEAM REACTIVITY COEFFICIENT | 1996 |
|
RU2136062C1 |
| ACTUATING ELEMENT OF NUCLEAR-REACTOR CONTROL AND PROTECTION SYSTEM | 2002 |
|
RU2231143C2 |
| SYSTEM FOR AUTOMATIC STABILIZATION OF NUCLEAR REACTOR POWER DISTRIBUTION | 0 |
|
SU701360A1 |
| METHOD FOR CONTROLLING AND PROTECTING A FAST NEUTRON NUCLEAR REACTOR AND A SYSTEM FOR ITS IMPLEMENTATION | 2022 |
|
RU2798480C1 |
| SYSTEM OF AUTOMATIC REGULATION OF FREQUENCY OF CURRENT IN THE NETWORK WITH PARTICIPATION OF NPP | 2016 |
|
RU2672559C1 |
| DEVICE FOR REGULATING SPATIAL INSTABILITY OF RELEASING POWER OF NUCLEAR REACTOR | 0 |
|
SU1823010A1 |
| ACTUATOR OF NUCLEAR-REACTOR CONTROL AND PROTECTION SYSTEM | 2000 |
|
RU2188469C2 |
| METHOD FOR OPERATING PRESSURIZED-TUBE URANIUM- GRAPHITE REACTOR AND CONTROL ELEMENT OF PRESSURIZED-TUBE URANIUM-GRAPHITE REACTOR | 2001 |
|
RU2190886C1 |
