국가/구분 |
United States(US) Patent
등록
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국제특허분류(IPC7판) |
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출원번호 |
US-0356950
(2003-02-03)
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발명자
/ 주소 |
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출원인 / 주소 |
- Westinghouse Electric Company LLC
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인용정보 |
피인용 횟수 :
14 인용 특허 :
8 |
초록
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An improved method of increasing the power output of an existing nuclear power plant includes increasing the thermal power output of the plant's nuclear island and constructing of an auxiliary BOP to handle the increased thermal power. The thermal power of the nuclear island can be increased such as
An improved method of increasing the power output of an existing nuclear power plant includes increasing the thermal power output of the plant's nuclear island and constructing of an auxiliary BOP to handle the increased thermal power. The thermal power of the nuclear island can be increased such as by increasing the thermal power of the plant's reactor, by replacing the plant's steam generator with one that is more efficient, and by increasing the flow rate and/or change in temperature of a coolant in a secondary cooling loop of the plant. The thermal power of the reactor can be increased such as by replacing existing cylindrical fuel rods with fuel rods having a relatively greater surface area to volume ratio and/or by increasing the flow rate and/or the change in temperature of a coolant of a primary cooling loop. The auxiliary BOP can be constructed while the plant is in operation, and can then be connected with the nuclear island during a maintenance operation on the reactor.
대표청구항
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1. A method of increasing the electrical power output of an existing nuclear power plant, the plant including a nuclear island and a balance of plant connected together, the nuclear island including a containment having an interior, a pressurized water reactor having a number of fuel rods that inclu
1. A method of increasing the electrical power output of an existing nuclear power plant, the plant including a nuclear island and a balance of plant connected together, the nuclear island including a containment having an interior, a pressurized water reactor having a number of fuel rods that include fissile material, and a steam generator, the reactor and the steam generator being disposed within the interior of the containment, the containment outputting thermal power, and the balance of plant outputting electrical power, the method comprising:operating the nuclear island during a first time period to output from the containment thermal power at a first rate: constructing an auxiliary balance of plant, at least a portion of said constructing an auxiliary balance of plant occurring during at least a portion of the first time period while the nuclear island is operating; connecting the auxiliary balance of plant with the nuclear island; increasing the thermal power output from the containment by operating the nuclear island during a second time period substantially subsequent to connection of the auxiliary balance of plant with the nuclear island to output from the containment thermal power at a second rate that is relatively greater than the first rate; delivering a portion of the thermal power to the auxiliary balance of plant; and outputting electrical power from the auxiliary balance of plant. 2. The method as set forth in claim 1, in whichthe reactor outputs thermal power; said increasing the thermal power output from the containment including; operating the reactor to output thermal power at a first rate; and increasing the thermal power output of the reactor by subsequently operating the reactor to output thermal power at a second, relatively higher rate. 3. The method as set forth in claim 2, in whichthe fuel rods have a surface area to volume ratio; said increasing the thermal power output of the reactor including increasing the surface area to volume ratio of the fuel rods by replacing at least a portion of the fuel rods with alternate fuel rods having a relatively higher surface area to volume ratio. 4. The method as set forth in claim 3, in whichthe fuel rods include cylindrical fuel rods; and said increasing the surface area to volume ratio of the fuel rods includes replacing the cylindrical fuel rods with annular fuel rods. 5. The method as set forth in claim 4, in whichsaid replacing the cylindrical fuel rods with annular fuel rods includes replacing the cylindrical fuel rods with annular fuel rods having an annular cladding within which is disposed fissile material. 6. The method as set forth in claim 3, in whichsaid increasing the thermal power output of the reactor includes installing neutron reflectors within the containment. 7. The method as set forth in claim 3, further comprising increasing the quantity of fissile material in the fuel rods.8. The method as set forth in claim 7, in which said increasing the quantity of fissile material in the fuel rods includes at least one of:replacing the fuel rods with other fuel rods that are relatively longer; installing neutron reflectors to increase the efficiency of neutron usage; replacing the fissile material with other fissile material having a lower neutron cross section; increasing the concentration of the fissile material compared with non-fissile material in the fuel rods; and increasing the density of the fissile material in order to accommodate more fissile material in the fuel rods. 9. The method as set forth in claim 2, in whichthe steam generator is a square-pitch steam generator; said increasing the thermal power output from the containment including replacing the square-pitch steam generator with a triangular-pitch steam generator. 10. The method as set forth in claim 1, in whichthe reactor outputs thermal power and includes a primary cooling loop carrying a primary coolant; the plant including a secondary cooling loop carrying a secondary coolant and being connected with the balance of plant and the auxiliary balance of plant; the steam generator thermally connecting together the primary and secondary cooling loops; said increasing the thermal power output from the containment including at least one of: increasing the thermal power output of the reactor; increasing the flow rate of the primary coolant; increasing the change in temperature of the primary coolant flowing through the steam generator; increasing the change in temperature of the primary coolant flowing through the reactor; increasing the flow rate of the secondary coolant; increasing the change in temperature of the secondary coolant flowing through the steam generator; and increasing the thermal efficiency of the steam generator. 11. The method as set forth in claim 1, further comprising:connecting the auxiliary balance of plant with the containment contemporaneously with the performance of a maintenance operation on the reactor. 12. The method as set forth in claim 11, further comprising:at least partially building the auxiliary balance of plant prior to initiating the maintenance operation on the reactor. 13. The method as set forth in claim 12, further comprising:at least partially building the auxiliary balance of plant while the power plant is operating. 14. The method as set forth in claim 1, further comprising:ceasing to generate electrical power from the balance of plant. 15. A method of increasing the electrical power output of an existing nuclear power plant substantially without a need of altering a containment of the plant, the plant including a nuclear island and a balance of plant connected together, the nuclear island including the containment which includes an interior, a pressurized water reactor having a number of fuel rods that include fissile material, and a steam generator, the or and the steam generator being disposed within the interior of the containment, the reactor outputting thermal power, and the balance of plant outputting electrical power, the method comprising:operating the nuclear island during a first time period to output from the reactor thermal power at a first rate; constructing an auxiliary balance of plant at least constructing an auxiliary balance of plant occurring during at least a portion of the first time period while the nuclear island is operating; thermally connecting the auxiliary balance of plant with the reactor; increasing the thermal power output from the containment by operating the nuclear island during a second time period substantially subsequent to connection of the auxiliary balance of plant with the reactor to output from the reactor thermal power at a second rate that is relatively greater than the first rate; and outputting electrical power from the auxiliary balance of plant. 16. The method as set forth in claim 15, in whichthe fuel rods have a surface area to volume ratio; said increasing the thermal power output of the reactor including increasing the surface area to volume ratio of the fuel rods by replacing at least a portion of the fuel rods with alternate fuel rods having a relatively higher surface area to volume ratio. 17. The method as set forth in claim 16, in whichthe fuel rods include cylindrical fuel rods; and said increasing the surface area to volume ratio of the fuel rods includes replacing the cylindrical fuel rods with annular fuel rods. 18. The method as set forth in claim 17, in whichsaid replacing the cylindrical fuel rods with annular fuel rods includes replacing the cylindrical fuel rods with annular fuel rods having an annular cladding within which is disposed fissile material. 19. The method as set forth in claim 15, further comprisingincreasing the quantity of fissile material in the fuel rods. 20. The method as set forth in claim 19, in whichsaid increasing the quantity of fissile material in the fuel rods includes least one of: replacing the fuel rods with other fuel rods that are relatively longer; installing neutron reflectors to increase the efficiency of neutron usage; replacing the fissile material with other fissile material having a lower neutron cross section; increasing the concentration of the fissile material compared with non-fissile material in the fuel rods; and increasing the density of the fissile material in order to accommodate more fissile material in the fuel rods. 21. The method as set forth in claim 15, in whichthe reactor includes a primary cooling loop crying a primary coolant; the plant including a secondary cooling loop carrying a secondary coolant and being connected with the balance of plant and the auxiliary balance of plant; the steam generator thermally connecting together the primary and secondary cooling loops; the method further comprising at least one of: increasing the flow rate of the primary coolant; increasing the change in temperature of the primary coolant flowing through the steam generator; increasing the change in temperature of the primary coolant flowing through the reactor; increasing the flow rate of the secondary coolant; increasing the change in temperature of the secondary coolant flowing through the steam generator; and increasing the thermal efficiency of the steam generator. 22. The method as set forth in claim 15, further comprising:connecting the auxiliary balance of plant with the containment during a scheduled shutdown of the reactor for the performance of a maintenance operation on reactor. 23. The method as set forth in claim 22, further comprising:at least partially building the auxiliary balance of plant prior to initiating the shutdown of the reactor. 24. The method as set forth in claim 23, further comprising:at least partially building the auxiliary balance of plant while the power plant is operating. 25. The method as set forth in claim 15, further comprising:modifying the reactor to increase the thermal power output thereof substantially without altering the volume occupied by the reactor; and replacing the steam generator to increase the efficiency thereof substantially without altering the volume occupied by the steam generator. 26. The method as set forth in claim 15, further comprising:ceasing to generate electrical power from the balance of plant.
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