CN114446503A - System of integrated small reactor nuclear power unit and reactor operation method - Google Patents
System of integrated small reactor nuclear power unit and reactor operation method Download PDFInfo
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- CN114446503A CN114446503A CN202111282323.0A CN202111282323A CN114446503A CN 114446503 A CN114446503 A CN 114446503A CN 202111282323 A CN202111282323 A CN 202111282323A CN 114446503 A CN114446503 A CN 114446503A
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D5/00—Arrangements of reactor and engine in which reactor-produced heat is converted into mechanical energy
- G21D5/02—Reactor and engine structurally combined, e.g. portable
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F22—STEAM GENERATION
- F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
- F22B1/00—Methods of steam generation characterised by form of heating method
- F22B1/02—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers
- F22B1/08—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers the heat carrier being steam
- F22B1/14—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers the heat carrier being steam coming in direct contact with water in bulk or in sprays
- F22B1/143—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers the heat carrier being steam coming in direct contact with water in bulk or in sprays in combination with a nuclear installation
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
Abstract
The invention belongs to the technical field of nuclear power units, and particularly discloses a system and a reactor operation method of an integrated small reactor nuclear power unit, which comprises an integrated reactor, a steam turbine generator unit, a main control system and a reactor operation method; the integrated reactor comprises a pressure vessel, a steam-water separator and a normal waste heat discharge system; a reactor control rod driving mechanism and a straight-flow steam generator are arranged in the pressure vessel, and an outlet of the straight-flow steam generator is connected with an inlet of the steam-water separator; the inlet and outlet of the normal waste heat discharge system are connected with a reactor core primary loop pipeline; the steam turbine generator unit comprises a steam turbine inlet steam regulating valve, a steam turbine, a condenser, a condensate pump, a deaerator, a water feeding pump, a water feeding regulating valve, a bypass steam discharge valve, a separator dewatering discharge valve and a generator; the invention can meet the internal and external requirements of the unit in the power operation stage, the starting and stopping processes, and has the capability of quickly adjusting the output power of the unit.
Description
Technical Field
The invention relates to the technical field of nuclear power units, in particular to a system of an integrated small reactor nuclear power unit and a reactor operation method.
Background
In recent years, with the development of nuclear energy technology, an integrated small reactor nuclear power generator is a new way for nuclear energy utilization. Compared with the traditional fossil energy, the nuclear energy has the advantages of low fuel cost, long refueling period, good operation stability, no pollutant discharge, no oxygen participation in nuclear reaction and the like. Therefore, the integrated small reactor has wide application space in the fields of scientific research facilities such as island power generation, offshore oil drilling platforms, icebreakers, deep sea submerging devices and the like, military equipment and civil equipment.
Compared with the traditional large pressurized water reactor commercial nuclear power station, the integrated small reactor nuclear power unit has obvious differences in the aspects of system structure, performance requirements and the like. In the aspect of system structure, because an advanced integrated reactor design is adopted, a direct-flow steam generator is arranged in the reactor, and the secondary side feed water generates superheated steam in a heat transfer pipe of the steam generator, the regulation strategy that the traditional large pressurized water reactor commercial nuclear power station maintains the liquid level of the natural circulation type steam generator by regulating the feed water flow is not applicable any more, and a new feed water regulation control strategy needs to be researched; in the aspect of performance requirements, a large pressurized water reactor commercial nuclear power unit generally does not participate in power peak regulation, the requirement on the power change rate is relatively low and is generally not higher than 5% RTP/min, the integrated small reactor nuclear power unit has various purposes, and the integrated small reactor nuclear power unit has a higher requirement on the change rate of the output power of the unit in a part of application scenes. Due to the differences, the integrated small reactor nuclear power unit is greatly different from the traditional large pressurized water reactor commercial nuclear power station in the aspects of a system thermodynamic structure, an operation control mode and the like, and a corresponding operation control strategy needs to be designed according to the requirements of users.
At present, the design of an integrated small reactor nuclear power unit is still in an exploration stage, the technical routes at home and abroad are various, and a unified and mature solution is not formed yet. Under the background, a feasible system of the integrated small reactor nuclear power generating unit with the rapid output power response capability and a reactor operation method are provided through mechanism analysis and scheme research, a new thought is provided for future nuclear energy utilization in China, and the method has positive significance.
Disclosure of Invention
The invention aims to provide a system of an integrated small reactor nuclear power unit and a reactor operation method, so as to solve the problems in the background technology.
In order to achieve the purpose, the invention provides the following technical scheme: a system of an integrated small reactor nuclear power unit and a reactor operation method comprise an integrated reactor, a steam turbine generator unit, a main control system and a stack operation method; the integrated reactor comprises a pressure vessel, a steam-water separator and a normal waste heat discharge system; a reactor control rod driving mechanism and a straight-flow steam generator are arranged in the pressure vessel, and an outlet of the straight-flow steam generator is connected with an inlet of the steam-water separator; the inlet and outlet of the normal waste heat discharge system are connected with a reactor core primary loop pipeline and used for leading out reactor core waste heat in the start-stop stage of the unit; the steam turbine generator unit comprises a steam turbine inlet steam regulating valve, a steam turbine, a condenser, a condensate pump, a deaerator, a water feed pump, a water feed regulating valve, a bypass steam discharge valve, a separator dewatering discharge valve and a generator; the steam turbine comprises a steam turbine inlet steam regulating valve, a condensate pump, a deaerator, a feed water pump, a feed water regulating valve and a steam turbine, wherein the inlet of the steam turbine inlet steam regulating valve is connected with the steam outlet of a steam-water separator, the outlet of the steam turbine inlet steam regulating valve is connected with the inlet of the steam turbine, the steam outlet of the steam turbine is connected with the inlet of the condenser, the outlet of the bottom of the condenser is connected with the inlet of the condensate pump, the outlet of the condensate pump is connected with the inlet of the deaerator, the outlet of the deaerator is connected with the inlet of the feed water pump, the outlet of the feed water pump is connected with the inlet of the feed water regulating valve, and the outlet of the feed water regulating valve is connected with the inlet of the straight-flow steam generator; an inlet of the bypass steam discharge valve is connected with a steam outlet of the steam-water separator, and an outlet of the bypass steam discharge valve is connected with an inlet of the condenser; the inlet of the separator hydrophobic discharge valve is connected with a drain outlet at the bottom of the steam-water separator, and the outlet of the separator hydrophobic discharge valve is connected with the inlet of the deaerator; the generator is connected with a rotor of the steam turbine; the main control system comprises a steam turbine steam control system, a reactor power control system, a bypass steam discharge control system, a feed water flow control system and a separator liquid level control system.
As a preferred technical scheme of the invention, the steam turbine steam control system has two modes of a power operation mode and a low-load mode; in the power operation mode, the steam regulating valve at the inlet of the steam turbine is used for maintaining the outlet pressure of the straight-flow steam generator to be constant; and in the low-load mode, the steam turbine inlet steam regulating valve regulates the steam flow of the steam turbine inlet according to the target power demand of the generator.
As a preferred technical scheme of the invention, the reactor power control system has two control modes, namely a manual control mode and an automatic control mode; in the manual control mode, the reactor power is manually controlled by an operator; in the automatic control mode, the reactor adopts a reactor following control strategy, the power of the nuclear island is changed along with the load change of the steam turbine set, and meanwhile, the average temperature of a primary circuit is kept constant.
As a preferred technical scheme of the invention, the bypass steam discharge control system has two modes of a temperature control mode and a pressure control mode; in the temperature control mode, the bypass steam discharge is used for preventing the average temperature of the primary circuit from being overhigh; in the pressure control mode, bypass steam venting is used to maintain the main steam header pressure constant.
As a preferred technical scheme of the invention, the water supply flow control system has two modes of a manual control mode and a power operation mode; under the manual control mode, the water supply flow is adjusted or maintained according to the instruction of an operator; and under the power operation mode, regulating the water supply flow according to the deviation of the target value and the actual value of the generating power of the unit, and responding to the external power supply requirement.
As a preferable technical scheme, the steam-water separator liquid level control system regulates the drainage flow in the separator according to the deviation of the separator liquid level and the setting value, and prevents steam from carrying water into the steam turbine to cause blade cavitation.
The invention also provides a pile machine operation method of the integrated small reactor nuclear power unit, which comprises a pile machine operation method of three stages, namely a unit power operation stage, a starting process and a normal shutdown process;
as a preferable technical scheme of the invention, the unit power operation stage refers to an operation stage of an automatic control mode that the reactor and the power are both larger than 15% of rated power and the reactor is put into a reactor and a machine. The operation method of the stage is as follows:
the reactor power control system is put into an automatic control mode of a reactor follower, the reactor power changes along with the power of a steam turbine, and the average temperature of a primary loop is maintained to be a constant value;
the water supply flow control system is put into a power operation mode, and the water supply flow of the steam generator is adjusted according to the deviation of the power generation power of the steam turbine and the target power to meet the external power requirement;
the steam turbine steam control system is put into a power operation mode, the steam flow of the steam turbine is adjusted according to the deviation between the measured value and the setting value of the outlet pressure of the steam generator, and the outlet pressure of the steam generator is kept constant;
the bypass steam discharge control system is put into a temperature control mode, the flow of bypass steam is adjusted according to the deviation between the average temperature measured value and the reference value of the primary circuit, and the average temperature of the primary circuit is prevented from exceeding the allowable range;
the steam-water separator liquid level control system adjusts the opening of the drain control valve according to the deviation of the steam-water separator liquid level and a set value, and leads drain water into the deaerator.
As a preferred embodiment of the present invention, the unit startup process refers to a process from the unit startup to the reactor start-up in the "stack-to-stack" automatic operation mode. The operation method of the stage is as follows:
in the process of heating and boosting the pressure of the first loop, the water supply flow control system is put into a manual control mode to maintain the constant flow of the water supply of the second loop at 15 percent of rated water supply flow; draining the drain water in the steam-water separator into a deaerator through a separator drain water regulating valve, and synchronously heating the feed water of the two loops by regulating the auxiliary heating steam flow of the deaerator;
the reactor power control system is put into a manual control mode, and the thermal power of the nuclear island is increased to about 15% from the thermal state zero power and is stabilized at the level;
the bypass steam discharge control system is put into a pressure control mode, the opening of a bypass steam discharge regulating valve is automatically regulated according to the pressure of the main steam pipe and the deviation of a setting value, and the pressure of the main steam pipe is maintained to be constant;
the steam turbine steam control system is put into a low-power mode to realize the impulse synchronization of the steam turbine; after grid connection, regulating the steam flow according to the deviation of the target value and the current value of the generated power, and increasing the generated power of the steam turbine to 15% and keeping the generated power at the level;
when the power of the reactor and the power of the steam turbine are both stabilized at 15 percent of rated power, the steam control system of the steam turbine is sequentially switched to a power operation mode, the feed water flow control system is switched to the power operation mode, the bypass steam discharge control system is switched to a temperature control mode, finally the reactor power control system is put into an automatic control mode of the reactor follower, and the starting process is finished.
As a preferred technical scheme of the invention, the normal shutdown process of the unit refers to a process from reactor exiting from the automatic control mode to reactor shutdown cooling. The operation method at the stage comprises the following steps:
when the power of the reactor and the steam turbine is reduced to 15 percent of the rated power level, the reactor exits from the automatic control mode of the reactor follower, is switched to the manual control mode, and is stabilized at the power level;
when the reactor is put into a manual control mode, the bypass steam discharge control system is sequentially switched to a pressure control mode, the feed water flow control system is switched to the manual control mode, and the feed water flow is kept constant at 15% of rated feed water flow;
the steam turbine steam control system exits from a power operation mode and is gradually closed according to a set speed until the steam turbine is stopped;
when the steam turbine is shut down, the reactor power control system reduces the reactor power in a manual control mode until the reactor shutdown normal waste heat discharge system is started, and when the average temperature of a primary loop is reduced to a set value, the secondary loop water supply system is shut down, and the shutdown process is finished.
Compared with the prior art, the invention has the beneficial effects that:
due to the structural particularity and the difference of application environments, the operation control mode of the integrated small reactor nuclear power unit is greatly different from that of the traditional large commercial nuclear power unit, and a unified and mature solution scheme is not formed in the industry at present; the invention provides a system of an integrated small reactor nuclear power unit and a reactor operation method, which can meet the internal and external requirements of the unit in the power operation stage, the starting and shutdown processes, have the capability of quickly adjusting the output power of the unit, provide a new idea for future nuclear energy utilization in China and have positive significance.
Drawings
FIG. 1 is a schematic view of the overall structure of the present invention;
FIG. 2 is a logic diagram of a reactor power control system in an automatic control mode of the automatic control system of the present invention;
FIG. 3 is a logic diagram of a feedwater flow control system in a power mode of operation according to the present invention;
FIG. 4 is a logic diagram of a steam turbine steam control system in a power mode of operation in accordance with the present invention;
FIG. 5 is a logic diagram of the steam turbine steam control system in the low load mode of the present invention;
FIG. 6 is a logic diagram of a steam-water separator liquid level control system of the present invention;
FIG. 7 is a logic diagram of the bypass steam vent control system in the temperature control mode of the present invention;
FIG. 8 is a logic diagram of the bypass steam vent control system in the pressure control mode of the present invention.
In the figure: 1. a pressure vessel; 2. a reactor control rod drive mechanism; 3. a once-through steam generator; 4. a steam-water separator; 5. a steam turbine inlet steam regulating valve; 6. a steam turbine; 7. a condenser; 8. a condensate pump; 9. a deaerator; 10. a feed pump; 11. a feed water regulating valve; 12. a bypass steam vent valve; 13. a separator drain valve; 14. a generator; 15. normal waste heat removal system; 16. a steam turbine steam control system; 17. a reactor power control system; 18. a vapor emission control system; 19. a feed water flow control system; 20. a separator liquid level control system.
Detailed Description
The technical solutions in the embodiments of the present invention will be clearly and completely described below with reference to the drawings in the embodiments of the present invention, and it is obvious that the described embodiments are only a part of the embodiments of the present invention, and not all of the embodiments. All other embodiments, which can be derived by a person skilled in the art from the embodiments given herein without making any creative effort, shall fall within the protection scope of the present invention.
In the description of the present invention, it should be noted that the terms "vertical", "upper", "lower", "horizontal", and the like indicate orientations or positional relationships based on those shown in the drawings, and are only for convenience of describing the present invention and simplifying the description, but do not indicate or imply that the referred device or element must have a specific orientation, be constructed in a specific orientation, and be operated, and thus, should not be construed as limiting the present invention.
In the description of the present invention, it should also be noted that, unless otherwise explicitly specified or limited, the terms "disposed," "mounted," "connected," and "connected" are to be construed broadly and may, for example, be fixedly connected, detachably connected, or integrally connected; can be mechanically or electrically connected; they may be connected directly or indirectly through intervening media, or they may be interconnected between two elements. The specific meanings of the above terms in the present invention can be understood by those skilled in the art according to specific situations.
Referring to fig. 1, the present invention provides a technical solution: a system of an integrated small reactor nuclear power unit and a reactor operation method comprise an integrated reactor, a steam turbine generator unit, a main control system and a stack operation method; the integrated reactor comprises a pressure vessel 1, a steam-water separator 4 and a normal waste heat discharge system 15; a reactor control rod driving mechanism 2 and a straight-flow steam generator 3 are arranged in the pressure vessel 1, and an outlet of the straight-flow steam generator 3 is connected with an inlet of a steam-water separator 4; an inlet and an outlet of the normal waste heat discharge system 15 are connected with a reactor core primary loop pipeline and used for leading out reactor core waste heat in the start-stop stage of the unit; the steam turbine generator unit comprises a steam turbine inlet steam regulating valve 5, a steam turbine 6, a condenser 7, a condensate pump 8, a deaerator 9, a feed pump 10, a feed regulating valve 11, a bypass steam discharge valve 12, a separator hydrophobic discharge valve 13 and a generator 14; an inlet of the steam turbine inlet steam regulating valve 5 is connected with a steam outlet of the steam-water separator 4, an outlet of the steam turbine inlet steam regulating valve 5 is connected with an inlet of a steam turbine 6, a steam outlet of the steam turbine 6 is connected with an inlet of a condenser 7, an outlet of the bottom of the condenser 7 is connected with an inlet of a condensate pump 8, an outlet of the condensate pump 8 is connected with an inlet of a deaerator 9, an outlet of the deaerator 9 is connected with an inlet of a water feed pump 10, an outlet of the water feed pump 10 is connected with an inlet of a water feed regulating valve 11, and an outlet of the water feed regulating valve 11 is connected with an inlet of the straight-flow steam generator 3; an inlet of the bypass steam discharge valve 12 is connected with a steam outlet of the steam-water separator 4, and an outlet of the bypass steam discharge valve 12 is connected with an inlet of the condenser 7; the inlet of the separator hydrophobic discharge valve 13 is connected with a hydrophobic port at the bottom of the steam-water separator 4, and the outlet of the separator hydrophobic discharge valve 13 is connected with the inlet of the deaerator 9; the generator 14 is connected with the rotor of the steam turbine 6; the control system includes a turbine steam control system 16, a reactor power control system 17, a bypass steam vent control system 18, a feedwater flow control system 19, and a separator level control system 20.
Furthermore, the reactor adopts an integrated design, and a through-flow steam generator 3 is arranged in the reactor to be used as a primary loop heat exchange device and a secondary loop heat exchange device.
Further, the steam turbine steam control system 16 has two modes, namely a power operation mode and a low-load mode; in the power operation mode, the steam turbine inlet steam regulating valve 5 is used for maintaining the outlet pressure of the once-through steam generator 3 constant; in the low load mode, the turbine inlet steam regulating valve 5 regulates the inlet steam flow of the turbine 6 according to the target power demand of the generator 14.
Further, the reactor power control system 17 has two control modes, i.e. a manual control mode and an automatic control mode; in the manual control mode, the reactor power is manually controlled by an operator; in the automatic control mode, the reactor adopts a reactor following control strategy, the power of the nuclear island is changed along with the load change of the steam turbine set, and meanwhile, the average temperature of a primary circuit is kept constant.
Further, the bypass steam vent control system 18 has two modes, i.e., a "temperature control mode" and a "pressure control mode"; in the temperature control mode, the bypass steam discharge is used for preventing the average temperature of the primary circuit from being overhigh; in the pressure control mode, bypass steam venting is used to maintain the main steam header pressure constant.
Furthermore, the feed water flow control system 19 has two modes, namely a manual control mode and a power running mode; under the manual control mode, the water supply flow is adjusted or maintained according to the instruction of an operator; and under the power operation mode, regulating the water supply flow according to the deviation of the target value and the actual value of the generating power of the unit, and responding to the external power supply requirement.
Further, the steam-water separator liquid level control system 20 adjusts the drainage flow rate in the separator according to the deviation between the separator liquid level and the setting value, and prevents steam from carrying water into the steam turbine 6 to cause blade cavitation.
The invention also provides a pile machine operation method of the integrated small reactor nuclear power unit, which comprises the following three stages of pile machine operation methods:
(1) the method for operating the reactor and the machine in the power operation stage of the machine set is an operation method in the automatic control mode stage when the power of the reactor and the machine is more than 15 percent and the reactor is put into the reactor and the machine;
(2) the operation method of the reactor in the starting process of the unit, namely the operation method of the process from the starting of the unit to the putting of the reactor into the reactor and the automatic control mode of the reactor;
(3) the method for operating the reactor during the normal shutdown process of the unit is an operation method from the process of reactor exiting from the automatic control mode to the reactor shutdown cooling.
Further, in the power operation stage of the unit, the reactor control rod driving mechanism is in an automatic control mode, the reactor power changes along with the load change of the steam turbine, and the basic logics of each control system are as follows:
as shown in fig. 2, the principle of the reactor power control system 17 in power operation mode: the deviation value of the current reactor power (normalized value) and the feedwater flow (normalized value) is used for representing the power mismatch component between the reactors; deviation of a measured average temperature value of a circuit from a reference value is used to characterize a temperature mismatch component of the reactor coolant. The power mismatch component is superposed with the temperature mismatch component after PI operation to form an adjusting signal of the control rod driving mechanism, and the constant of the average temperature of a loop is maintained.
As shown in fig. 3, the feed water flow control system 19 principle in power mode of operation: the deviation between the target load signal of the unit and the load signal of the steam turbine 6 represented by the current main water supply flow forms a feedback component of the power control system; the change rate of the steam flow of the steam turbine 6 forms a feed-forward component of the power control system after calculation. After the feedforward and the feedback components are superposed, a valve opening signal of the main feed water regulating valve is obtained through PID operation, so that the main feed water flow changes along with the change of the target load of the steam turbine.
As shown in FIG. 4, the steam turbine steam control system 16 principle in power mode of operation: and obtaining an opening signal of the steam regulating valve of the steam turbine after PI operation of the deviation between the measured value and the setting value of the outlet pressure of the direct-flow steam generator 3, and using the opening signal to maintain the outlet pressure of the direct-flow steam generator 3 constant.
As shown in the attached FIG. 6, the principle of the steam-water separator 4 liquid level control system 20 is as follows: when the level of the drained water in the steam-water separator 4 exceeds a set value, a drain regulating valve of the steam-water separator 4 is automatically opened, and the drained water is sent to a hot well of a condenser 7. Under the working conditions of starting, stopping, faults and the like, working media at the outlet of the straight-flow steam generator 3 can be supercooled water, saturated water or wet steam, and through a steam-water separation link, steam can be prevented from carrying water into the steam turbine 6 to cause damage to turbine blades.
As shown in FIG. 7, the bypass steam vent control system 18 principle in temperature control mode: the unit is in a power operating phase and the bypass steam vent control system 18 is put into a "temperature control mode". When the load shedding of the steam turbine 6 or the power of the steam turbine is reduced too fast, the deviation between the average temperature measured value and the reference value of the primary circuit exceeds the allowable range, the bypass steam discharge regulating valve 12 is opened, the flow of bypass steam is increased, the heat of the primary circuit is led out in an accelerated manner, and the average temperature of the primary circuit is kept stable; when the reactor is in emergency shutdown, the deviation between the measured value of the average temperature of the primary circuit and the set value (unloaded temperature) exceeds the allowable range, the bypass steam discharge regulating valve 12 is opened, the flow of the bypass steam is increased, the heat of the primary circuit is led out in an accelerated mode, and the stability of the average temperature of the primary circuit is maintained.
Further, in the unit starting process, in order to realize the coordinated operation of the reactors of the integrated small reactor nuclear power unit, the following key steps are required to be executed, including but not limited to:
the method comprises the following steps: completing respective preparation work before the side start of the reactor and the turbine;
step two: heating and pressurizing a primary circuit, and leading out the heat of the reactor core by a normal waste heat discharge system 15 in the period;
step three: when the two loops meet the starting condition, starting the condensate pump 8 and the water supply pump 10, and maintaining the water supply flow to be about 15% of the rated water supply flow through the water supply regulating valve 9; at this time, since the feed water is not heated in the once-through steam generator 3, the feed water still flows into the steam-water separator 4 in a supercooled water state;
step four: the steam-water separator hydrophobic discharge valve 13 automatically adjusts the opening of the valve according to the deviation of the liquid level of the steam-water separator and a reference value, and leads hydrophobic water at the bottom of the steam-water separator into a deaerator; the auxiliary heating steam flow entering the deaerator is adjusted to synchronously heat the feed water of the two loops;
step five: when the secondary side water supply flow is stably established and the average temperature of the primary loop rises to a set value, the normal waste heat discharging system 15 is shut down;
step six: the reactor power control system is set in a manual control mode, and the rod position of a control rod is determined by the target rod position and the rod lifting speed input by an operator; in the manual mode, the reactor power is increased to about 15% of the rated power and is stabilized at the level; in the process, steam is formed in the once-through steam generator 3 along with the gradual rise of the heat power of the primary circuit;
step seven: when the steam pressure at the top of the steam-water separator exceeds a set value, the steam turbine bypass regulating valve 12 is opened and put into a pressure control mode, and the control principle is shown in FIG. 7; automatically adjusting the opening of a bypass steam discharge adjusting valve according to the deviation of the pressure of the main steam main pipe and a setting value, and discharging steam at the upper part of the steam-water separator to a steam side space of a condenser;
step eight: opening a steam regulating valve 5 of the steam turbine, and starting the steam turbine to warm up and rotate in a rush mode; in the process of the impulse rotation, the steam regulating valve 5 of the steam turbine receives a valve position instruction of a power-frequency electro-hydraulic regulating system of the steam turbine, and the control principle is shown in fig. 5; at the moment, the deviation between the measured value of the rotating speed of the steam turbine and the target value forms a frequency regulation component after PI operation, and after the frequency regulation component is superposed with a power regulation component (the component is 0 in the impulse phase), the opening degree of a steam regulating valve 5 of the steam turbine is regulated together;
step nine: when the rotating speed of the steam turbine reaches the target rotating speed, the breaker at the outlet of the generator 14 is closed, and the generator 14 supplies power to the outside;
step ten: the steam regulating valve 5 of the steam turbine raises the power to about 15 percent of rated power under the control of a power-frequency electro-hydraulic regulating system of the steam turbine and keeps stable operation, and the control principle is shown in figure 5; at the moment, the deviation between the measured value and the target value of the power generated by the steam turbine forms a power regulation component after PI operation, and the power regulation component and the frequency regulation component are superposed to jointly regulate the opening degree of the steam regulating valve 5 of the steam turbine;
step eleven: after the power of the stack and the power of the power are stabilized at about 15 percent of rated power, the steam flow regulating valve 5 of the steam turbine is switched to a power operation mode (as shown in figure 4); adjusting the opening of a steam regulating valve 5 of a steam turbine at the inlet of the steam turbine according to the deviation of the pressure at the outlet of the direct-flow steam generator 3 and the reference pressure, and maintaining the pressure at the outlet of the direct-flow steam generator 3 to be stable; since the bypass steam control valve 12 is in the "pressure control mode" (as shown in fig. 8), the outlet pressure of the once-through steam generator 3 is stabilized at the target value, and therefore, the mode switching of the steam flow control valve 5 of the steam turbine does not generate obvious disturbance to the steam flow and the steam pressure;
step twelve: the feed water flow regulating valve 11 is switched to a power running mode (shown in figure 3), and the initial value of the target load is 15% of the rated load; because the feedwater flow and the turbine power have both reached and maintained at about 15% of the rated values before the mode switch, the switch does not cause significant disturbances to the turbine operation;
step thirteen: the bypass steam vent regulator valve 12 is switched to "temperature control mode" (as shown in fig. 7); the bypass steam discharge valve 12 automatically adjusts the opening of the valve according to the deviation of the average temperature measured value of the primary circuit and the reference temperature, and when the deviation is overlarge, the bypass steam discharge valve 12 is opened and is used for preventing the primary circuit from being overheated due to the power mismatch of the primary circuit and the secondary circuit;
fourteen steps: the operator puts the reactor control system into "automatic control mode" (as shown in fig. 2); the unit enters a 'stack following machine' operation mode, and the reactor power changes along with the load change of a steam turbine; the operator can set a new target load and the unit continues to ramp up.
Further, in the shutdown process of the unit, in order to realize the reactor-machine coordination operation of the integrated small reactor nuclear power unit, the following steps are executed:
the method comprises the following steps: when the power of the reactor and the steam turbine is reduced to about 15 percent of rated power level, the reactor exits from the automatic control mode of the reactor follower, is switched to the manual control mode, and is stabilized at the power level;
step two: the bypass steam vent control valve 12 is switched to a "pressure control mode" with the control principle as shown in fig. 8; automatically adjusting the opening of the bypass steam discharge valve 12 according to the deviation of the main steam main pipe pressure and the setting value, and maintaining the main steam main pipe pressure stable;
step three: the feed water flow regulating valve 11 is switched to a manual control mode, and a constant feed water flow (about 15 percent of rated flow) is maintained to pass through the once-through steam generator 3 so as to ensure that heat generated by a loop can be taken away;
step four: the steam regulating valve 5 at the inlet of the steam turbine exits from the power running mode and is gradually closed according to a set speed; the power generation power of the steam turbine 6 is gradually reduced along with the gradual reduction of the steam flow at the inlet of the steam turbine 6;
step five: after the power of the generator 14 is reduced and reverse power protection is triggered, the breaker at the outlet of the generator 14 is automatically disconnected;
step six: the steam regulating valve 5 at the inlet of the steam turbine is continuously closed until the steam regulating valve is completely closed, and the steam turbine 6 is stopped;
step seven: the operator reduces the reactor power in the manual mode until the reactor is shut down;
step eight: when the average temperature of the primary loop is reduced to a set value, the normal waste heat discharging system 15 is started to lead out the heat generated by the reactor core;
step nine: after the normal waste heat discharging system 15 operates stably, the secondary side water supply system is shut down;
step ten: after the average temperature of the primary loop further drops to an allowable value, the normal waste heat discharge system 15 is shut down;
step eleven: and finishing the maintenance and the repair work after the shutdown of the reactor and the steam turbine 6.
Although embodiments of the present invention have been shown and described, it will be appreciated by those skilled in the art that changes, modifications, substitutions and alterations can be made in these embodiments without departing from the principles and spirit of the invention, the scope of which is defined in the appended claims and their equivalents.
Claims (10)
1. A system of an integrated small reactor nuclear power unit is characterized by comprising an integrated reactor, a steam turbine generator unit and a main control system; the integrated reactor comprises a pressure vessel (1), a steam-water separator (4) and a normal waste heat discharge system (15); a reactor control rod driving mechanism (2) and a straight-flow steam generator (3) are arranged in the pressure vessel (1), and an outlet of the straight-flow steam generator (3) is connected with an inlet of a steam-water separator (4); an inlet and an outlet of the normal waste heat discharge system (15) are connected with a reactor core primary loop pipeline and used for leading out reactor core waste heat in the start-stop stage of the unit; the steam turbine generator unit comprises a steam turbine inlet steam regulating valve (5), a steam turbine (6), a condenser (7), a condensate pump (8), a deaerator (9), a water feeding pump (10), a water feeding regulating valve (11), a bypass steam discharge valve (12), a separator hydrophobic discharge valve (13) and a generator (14); the inlet of the steam turbine inlet steam regulating valve (5) is connected with the steam outlet of the steam-water separator (4), the outlet of the steam turbine inlet steam regulating valve (5) is connected with the inlet of the steam turbine (6), the steam outlet of the steam turbine (6) is connected with the inlet of the condenser (7), the outlet at the bottom of the condenser (7) is connected with the inlet of the condensate pump (8), the outlet of the condensate pump (8) is connected with the inlet of the deaerator (9), the outlet of the deaerator (9) is connected with the inlet of the feed pump (10), the outlet of the feed pump (10) is connected with the inlet of the feed water regulating valve (11), and the outlet of the feed water regulating valve (11) is connected with the inlet of the once-through steam generator (3); an inlet of the bypass steam discharge valve (12) is connected with a steam outlet of the steam-water separator (4), and an outlet of the bypass steam discharge valve (12) is connected with an inlet of the condenser (7); an inlet of the separator hydrophobic discharge valve (13) is connected with a drain outlet at the bottom of the steam-water separator (4), and an outlet of the separator hydrophobic discharge valve (13) is connected with an inlet of the deaerator (9); the generator (14) is connected with the rotor of the steam turbine (6); the main control system comprises a steam turbine steam control system (16), a reactor power control system (17), a bypass steam discharge control system (18), a feed water flow control system (19) and a separator liquid level control system (20).
2. The system of an integrated mini-reactor nuclear power plant as in claim 1, wherein: the steam turbine steam control system (16) has two modes of a power operation mode and a low-load mode; in the power operation mode, a steam regulating valve (5) at the inlet of the steam turbine is used for maintaining the outlet pressure of the once-through steam generator (3) constant; in the low-load mode, the steam turbine inlet steam regulating valve (5) regulates the steam flow at the inlet of the steam turbine (6) according to the target power demand of the generator (14).
3. The system of an integrated mini-reactor nuclear power plant as in claim 1, wherein: the reactor power control system (17) has two control modes, namely a manual control mode and an automatic control mode; in the manual control mode, the reactor power is manually controlled by an operator; in the automatic control mode, the reactor adopts a reactor following control strategy, the power of the nuclear island is changed along with the load change of the steam turbine set, and meanwhile, the average temperature of a primary circuit is kept constant.
4. The system of an integrated mini-reactor nuclear power plant as in claim 1, wherein: the bypass steam discharge control system (18) has two modes of a temperature control mode and a pressure control mode; in the temperature control mode, the bypass steam discharge is used for preventing the average temperature of the primary circuit from being overhigh; in the pressure control mode, bypass steam venting is used to maintain the main steam header pressure constant.
5. The system of an integrated mini-reactor nuclear power plant as in claim 1, wherein: the water supply flow control system (19) has two modes of a manual control mode and a power running mode; under the manual control mode, the water supply flow is adjusted or maintained according to the instruction of an operator; and under the power operation mode, regulating the water supply flow according to the deviation of the target value and the actual value of the generating power of the unit, and responding to the external power supply requirement.
6. The system of an integrated mini-reactor nuclear power plant as in claim 1, wherein: and the steam-water separator liquid level control system (20) regulates the drainage flow in the separator according to the deviation of the separator liquid level and the setting value.
7. The method for operating the reactor of the integrated small reactor nuclear power unit according to any one of claims 1 to 6, characterized by comprising the following three-stage reactor operation method:
(1) the method for operating the reactor in the power operation stage of the unit is an operation method in the 'automatic control mode' stage when the reactor is put into a reactor and the machine, wherein the average power of the reactor and the machine is more than 15%;
(2) the operation method of the reactor in the starting process of the unit, namely the operation method of the process from the starting of the unit to the putting of the reactor into the reactor and the automatic control mode of the reactor;
(3) the method for operating the reactor in the normal shutdown process of the unit is an operation method from the process that the reactor exits from the automatic control mode to the shutdown and cooling of the reactor.
8. The method for operating the reactor of the integrated small-sized reactor nuclear power unit according to claim 7, wherein the unit power operation stage is as follows:
(1) the reactor power control system (17) is put into an automatic control mode of the reactor-follower, the reactor power changes along with the power of the steam turbine, and the average temperature of a primary loop is maintained to be a constant value;
(2) the water supply flow control system (19) is put into a power operation mode, and the water supply flow of the steam generator is adjusted according to the deviation of the power generation power of the steam turbine and the target power to meet the external power requirement;
(3) the steam turbine steam control system (16) is put into a power operation mode, the steam flow of the steam turbine is adjusted according to the deviation between the measured value and the setting value of the outlet pressure of the steam generator, and the outlet pressure of the steam generator is kept constant;
(4) the bypass steam discharge control system (18) is put into a temperature control mode, the flow of bypass steam is adjusted according to the deviation between the average temperature measured value and the reference value of the primary circuit, and the average temperature of the primary circuit is prevented from exceeding the allowable range;
(5) the steam-water separator liquid level control system (20) adjusts the opening of the drain regulating valve according to the deviation of the liquid level of the steam-water separator (4) and a set value, and leads drain water into the deaerator (9).
9. The method for operating the reactor of the integrated small-sized reactor nuclear power unit according to claim 7, characterized in that the starting process of the unit is as follows:
(1) in the process of heating and boosting the pressure of the first loop, the water supply flow control system (19) is put into a manual control mode to maintain the constant flow of the water supply of the second loop at 15 percent of rated water supply flow; draining the drain water in the steam-water separator (4) into a deaerator (9) through a separator drain water regulating valve (13), and synchronously heating the feed water of the two loops by regulating the auxiliary heating steam flow of the deaerator (9);
(2) the reactor power control system (17) is put into a manual control mode, and the thermal power of the nuclear island is increased to about 15% from the thermal state zero power and is stabilized at the level;
(3) the bypass steam discharge control system (18) is put into a pressure control mode, the opening of the bypass steam discharge regulating valve (12) is automatically regulated according to the deviation of the main steam main pipe pressure and a setting value, and the main steam main pipe pressure is maintained to be constant;
(4) the steam turbine steam control system (16) is put into a low-power mode to realize the impulse-to-grid connection of the steam turbine (6); after grid connection, regulating the steam flow according to the deviation of the target value and the current value of the generated power, and increasing the generated power of the steam turbine (6) to 15% of rated generated power and keeping the generated power at the level;
(5) when the power of the reactor and the power of the steam turbine (6) are stabilized at 15% of rated power, the steam control system (16) of the steam turbine is sequentially switched to a power operation mode, the feed water flow control system (19) is switched to the power operation mode, the bypass steam discharge control system (18) is switched to a temperature control mode, finally the reactor power control system (17) is put into an automatic control mode of the reactor-following machine, and the starting process is finished.
10. The method for operating the reactor of the integrated small-sized reactor nuclear power unit according to claim 7, wherein the normal shutdown process of the unit is as follows:
(1) when the power of the reactor and the steam turbine (6) is reduced to 15 percent of the rated power level, the reactor exits from the automatic control mode of the reactor follower, is switched to the manual control mode, and is stabilized at the power level;
(2) when the reactor is put into a manual control mode, the bypass steam discharge control system (18) is sequentially switched to a pressure control mode, the feed water flow control system (19) is switched to the manual control mode, and the feed water flow is kept constant at 15% of the rated feed water flow;
(3) the steam turbine steam control system (16) exits the power operation mode and is gradually closed according to a set speed until the steam turbine (6) stops;
(4) when the steam turbine (6) is shut down, the reactor power control system (17) reduces the reactor power in a manual control mode until the reactor shutdown normal waste heat discharge system (15) is started, and when the average temperature of the first loop is reduced to a set value, the water supply system of the second loop is shut down, and the shutdown process is finished.
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Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN115416833A (en) * | 2022-08-09 | 2022-12-02 | 中国船舶重工集团公司第七一九研究所 | Dry-wet alternating wide parameter start-stop system and control method |
| WO2023236477A1 (en) * | 2022-06-10 | 2023-12-14 | 中广核研究院有限公司 | Steam turbine protection apparatus, system and method for pressurized water reactor |
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Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO2023236477A1 (en) * | 2022-06-10 | 2023-12-14 | 中广核研究院有限公司 | Steam turbine protection apparatus, system and method for pressurized water reactor |
| CN115416833A (en) * | 2022-08-09 | 2022-12-02 | 中国船舶重工集团公司第七一九研究所 | Dry-wet alternating wide parameter start-stop system and control method |
| CN115416833B (en) * | 2022-08-09 | 2024-04-02 | 中国船舶集团有限公司第七一九研究所 | Dry-wet alternate wide-parameter start-stop system and control method |
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