Patent Number: 052934110
Section: claims

1. A boiling water type nuclear reactor power control method, comprising the steps of: feeding water with a plurality of first pumps to the nuclear reactor;  generating a trip signal when one of the first pumps supplying feed water to the nuclear reactor is tripped; and  controlling the nuclear reactor power to be at a first value of at least 80 percent of rated output power prior to any of said first pumps being tripped and reducing the power in the nuclear reactor in response to the trip signal by first decreasing the speed of a recirculation pump providing core flow to a core of the nuclear reactor to provide a core flow corresponding to a nuclear reactor power of a second value less than said first value.  a plurality of first pump means for feeding feed water to the nuclear reactor;  trip detection means for outputting a trip signal when one of the first pump means for supplying feed water to the nuclear reactor is tripped, said nuclear reactor operating at a predetermined first level of nuclear reactor power when said one of the first pump means is tripped;  first control means responsive to said trip signal;  reduction means responsive to said first control means for reducing circulation of core flow in the core of the nuclear reactor sufficiently to reduce power;  said first control means controlling said reduction means to first reduce the circulation of core flow in response to said trip signal;  second reduction means including a variation means for determining and generating a mismatched amount corresponding to a difference between the flow of steam discharged from said nuclear reactor and the flow of the feed water after the trip signal is generated, and  second control means for controlling and reducing the nuclear reactor power to a predetermined second level from said first level based upon the mismatched amount.  means for determining and generating a mismatched amount corresponding to a difference between the flow of steam discharged from said nuclear reactor and the flow of the feed water after the trip signal is generated, and  means for controlling the nuclear reactor power based upon the mismatched amount.  a plurality of first pumps for supplying feed water to the nuclear reactor;  a second pump circulating cooling water in the core in said nuclear reactor;  trip detection means for generating a trip signal when one of said first pumps is tripped;  first output control means to output a first control signal for operating the nuclear reactor at a first level of power when none of said first pumps is tripped;  second output control means to output a second control signal for operating the nuclear reactor at a second level of power, less than said first level, when one of said first pumps is tripped;  selection control means for switching control from said first output control means to said second output control means; and  reactor power reduction means for first reducing the speed of said second pump in response to generating said trip signal for reducing the nuclear power and then switching said selection control means to further reduce the nuclear reactor power to said second level from said first level.  a plurality of first pumps supplying feed water to the nuclear reactor;  a second pump circulating cooling water in the core in said nuclear reactor;  trip detection means for generating a trip signal when one of said first pumps is tripped;  core flow control means for controlling the speed of said second pump;  control rods mounted for insertion into the core;  control rod control means for controlling operation of said control rods;  first output control means to output a first control signal for operating the nuclear reactor at a first level of power when none of said first pumps is tripped;  second output control means to output a second control signal for operating the nuclear reactor at a second level of power;  said core flow control means controlling said second pump based upon the output signal from said second output control means and said first output control means;  said control rod control means controlling selected control rods based on the output signal of said second output control means and said first output control means; and  reactor power reduction means for first reducing the speed of said second pump in response to generating said trip signal and then switching operation to said second control means to further reduce the nuclear reactor power to said second level from said first level.  controlling nuclear reactor power in response to a first nuclear reactor power level set at a first predetermined value corresponding to a required output of a generator driven by the nuclear reactor under normal operation of a feed water supplying system;  detecting an abnormality in the feed water supplying system;  reducing the nuclear reactor power by first decreasing core flow in response to said detecting of the abnormality; and then  switching the nuclear reactor power level to a predetermined second level lower than said first level and corresponding to the specific abnormality detected, and continuing said controlling at the lower level.  operating said nuclear reactor at a predetermined first level of power;  detecting an abnormality of the feed water supplying system for the nuclear reactor;  first reducing speed of a pump circulating cooling liquid in the core in the nuclear reactor when the abnormality is detected;  thereafter, detecting a mismatched amount between flow of steam discharged from the nuclear reactor and flow of the feed water; and then  reducing the nuclear reactor power to a predetermined second level of power less than said first level after said reducing speed step based upon the mismatched amount.  operating said nuclear reactor at a predetermined first level of power  detecting an abnormality by only measuring characteristics of the feed water supplying system, which cause a flow of feed water to decrease abnormally;  reducing the nuclear reactor power in response to said detected abnormality by first reducing a speed of a recirculation pump providing core flow to a core in the nuclear reactor to a speed corresponding to a nuclear reactor power lower than said first nuclear reactor power; and  thereafter, further reducing said nuclear reactor power to a predetermined second level lower than said first level of nuclear reactor power.  operating said nuclear reactor at a predetermined first level of power;  detecting an abnormality of the feed water supplying system;  first reducing recirculation cooling flow within a core of the nuclear reactor, when the abnormality is detected, to a core flow corresponding to a nuclear reactor power lower than said first level by decreasing a speed of a pump providing recirculating cooling water in the core of the nuclear reactor; and  thereafter further reducing nuclear reactor power to a predetermined second level less than said first level that prevents over speed of the others of the pumps that remain operating for supplying feed water. 2. A nuclear reactor power control method according to claim 1, wherein said reducing reduces the nuclear reactor power in accordance with a mismatched amount between the flow of steam discharged from the nuclear reactor and the flow of the feed water. 3. The nuclear reactor power control method of claim 1, wherein said reducing further includes adjusting selected control rods based upon a mismatched amount between a flow of the steam discharged from the nuclear reactor and the flow of the feed water. 4. The nuclear reactor power control method of claim 1, wherein said reducing reduces the nuclear reactor power to a level that prevents overspeed of the other first pumps under operation to supply feed water. 5. A nuclear reactor power control device for a boiling water type nuclear reactor, comprising: 6. The nuclear reactor power control device of claim 5, including: 7. The nuclear reactor power control device of claim 5, wherein said reduction means includes means to output a control signal to reduce the nuclear reactor power to a level that prevents overspeed of other ones of said first pump means still in operation and means for controlling the nuclear reactor power based upon the control signal. 8. The nuclear reactor power control device of claim 5, wherein said trip detection means sets the trip signal to a value to reduce the nuclear reactor power to a fixed value having a lower level than the nuclear reactor power at the moment of the output of the trip signal. 9. A nuclear reactor power control device according to claim 5, wherein said means for controlling the nuclear reactor power is means for controlling insertion of selected control rods into the core. 10. A nuclear reactor power control device for a boiling water type nuclear reactor, comprising: 11. A nuclear reactor power control device according to claim 10, wherein a part of said first output control means is commonly used by said second output control means. 12. A nuclear reactor power control device according to claim 10, including core flow control flow for controlling the speed of said second pump in response to the second control signal, control rods, control rod control means for controlling operation of said control rods. third output control means to output a third control signal for controlling selected control rods with said control rod control means. 13. A nuclear reactor power control device for a boiling water type nuclear reactor, comprising: 14. A method for controlling reactor power of a boiling water type nuclear reactor, comprising: 15. A method for controlling reactor power of a boiling water type nuclear reactor, comprising: 16. A method for controlling reactor power of a boiling water type nuclear reactor in response to an abnormality of a feed water supplying system, comprising: 17. A method for controlling reactor power of a boiling water type nuclear reactor in response to an abnormality of a feed water supplying system, said feed water being supplied by a plurality of pumps, comprising: