CN114944236A - System and method for controlling power of reactor in pile-follower mode - Google Patents

System and method for controlling power of reactor in pile-follower mode Download PDF

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Publication number
CN114944236A
CN114944236A CN202210577093.9A CN202210577093A CN114944236A CN 114944236 A CN114944236 A CN 114944236A CN 202210577093 A CN202210577093 A CN 202210577093A CN 114944236 A CN114944236 A CN 114944236A
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module
power
output
reactor
control
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CN202210577093.9A
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Inventor
姚尧
余俨
梁舒婷
常重喜
叶林
赵峰
马喜强
黄鹏
王磊
赵敬锴
张建刚
侯加麟
徐浩凇
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Xian Thermal Power Research Institute Co Ltd
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Xian Thermal Power Research Institute Co Ltd
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Priority to CN202210577093.9A priority Critical patent/CN114944236A/en
Publication of CN114944236A publication Critical patent/CN114944236A/en
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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C17/00—Monitoring; Testing ; Maintaining
    • G21C17/10—Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
    • G21C17/112—Measuring temperature
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C17/00—Monitoring; Testing ; Maintaining
    • G21C17/06—Devices or arrangements for monitoring or testing fuel or fuel elements outside the reactor core, e.g. for burn-up, for contamination
    • 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
    • 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
    • Y02E30/30—Nuclear fission reactors

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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Control Of Turbines (AREA)

Abstract

The invention discloses a reactor-follower mode reactor power control system and a method, which comprises a reactor power measuring module, a turbine impulse stage pressure measuring module, a loop average temperature measuring module, a reactor power output module, a turbine power output module, a loop reference temperature output module, a loop average temperature output module, a power deviation data processing module, a temperature deviation data processing module, a selector module, an on-off device, a delay control module, a control rod direction and speed logic module and a control rod driving mechanism.

Description

System and method for controlling power of reactor in pile-follower mode
Technical Field
The invention belongs to the field of nuclear reactor power control, and relates to a reactor heel machine mode reactor power control system and method.
Background
With the reform of national energy policy, the operation mode of the nuclear power plant is gradually changed from the original base load operation into the peak regulation or frequency modulation participating in the power grid. The machine following reactor mode (turbine following reactor) designed by the original nuclear power plant is not suitable for the requirement of a power grid. In the stack-tracking mode, if the power control mode is adopted independently, the temperature of a loop can deviate from a normal operation curve; the temperature control mode is independently adopted, because the reactor capacity is large, the temperature change always lags behind the change of the reactor power, the feedback control speed is slow, and the oscillation of a control system or the poor control stability are easily caused. A power and temperature combined control mode is adopted in part of nuclear power plants, power deviation and temperature deviation are superposed, target deviation value is artificially expanded, a power control system is caused to act frequently, obvious control overshoot is generated, and the requirement of a steam turbine for load tracking by automatic control of reactor power cannot be met.
Disclosure of Invention
The invention aims to overcome the defects of the prior art and provides a reactor power control system and a method of a reactor-following mode, which can meet the requirement of a steam turbine for load tracking by automatically controlling the reactor power.
In order to achieve the aim, the reactor power control system of the reactor follower mode comprises a reactor power measuring module, a turbine impulse stage pressure measuring module, a loop average temperature measuring module, a reactor power output module, a turbine power output module, a loop reference temperature output module, a loop average temperature output module, a power deviation data processing module, a temperature deviation data processing module, a selector module, an on-off device, a delay control module, a control rod direction and speed logic module and a control rod driving mechanism;
the output end of the reactor power measuring module is connected with the input end of the reactor power output module, the output end of the reactor power output module is connected with the input end of the power deviation data processing module, the output end of the turbine impulse stage pressure measuring module is connected with the input end of the turbine power output module and the input end of a loop reference temperature output module, the output end of the loop average temperature measuring module is connected with the input end of the loop average temperature output module, the output end of the loop reference temperature output module and the output end of the loop average temperature output module are connected with the input end of the selector module, the output end of the power deviation data processing module is connected with the input end of the selector module and the input end of the control rod direction and speed logic module, and the output end of the selector module is connected with the control end of the on-off device, the output end of the temperature deviation data processing module is connected with the input end of the on-off device, the output end of the on-off device is connected with the input end of the delay control module, the output end of the delay control module is connected with the input end of the control rod direction and speed logic module, and the output end of the control rod direction and speed logic module is connected with the control end of the control rod driving mechanism.
The invention relates to a power control method of a reactor heel machine mode reactor, which comprises the following steps:
1) according to the reactor power output by the reactor power measuring module, the reactor real-time power signal P is calculated by the reactor power output module N (ii) a According to impulse of steam turbineThe turbine impulse stage pressure output by the stage pressure measuring module is calculated through the turbine power output module T ；
2) Calculating reactor power P by power deviation data processing module N With turbine power P T The calculated power deviation delta P is input into a selector module and a control rod direction and speed logic module;
3) inputting the signal output by the selector module into the on-off device to control the on-off of the on-off device;
4) when the power deviation delta P is larger than or equal to the preset deviation, the on-off device locking temperature deviation data processing module calculates a temperature deviation signal, and when the power deviation delta P exceeds a dead zone value, the control rod direction and speed logic module generates a control rod lifting/inserting instruction, and then controls a control rod driving mechanism to enable the power deviation delta P to be lower than the dead zone value;
5) calculating a primary circuit coolant reference temperature T through a primary circuit reference temperature output module according to the turbine impulse stage pressure output by the turbine impulse stage pressure measuring module ref (ii) a Calculating the average temperature T of the coolant of the primary circuit through the average temperature output module of the primary circuit according to the average temperature of the primary circuit output by the average temperature measurement module of the primary circuit avg ；
6) Calculating a reference loop coolant temperature T by a temperature deviation data processing module ref And the average temperature T avg Temperature deviation Δ T of (d);
7) when the power deviation delta P is lower than the preset deviation, the control rod direction and speed logic module does not send a power control signal, the on-off device does not lock the temperature deviation signal generated by the temperature deviation data processing module, and after the control signal generated by the temperature deviation data processing module is delayed by the delay control module, a control rod lifting/inserting instruction is generated by the control rod direction and speed logic module to control a control rod driving mechanism to control the coolant temperature T of a loop avg And (4) adjusting.
The invention has the following beneficial effects:
when the system and the method for controlling the power of the reactor-following model reactor are operated specifically, the deviation of the nuclear power of the reactor and the power of a steam turbine is taken as a priority adjusting signal to adjust the power deviation of the reactor in a limited way; the deviation between the temperature measured by a reactor loop and the reference temperature generated by a steam turbine is taken as an auxiliary adjusting signal, when the power deviation is in a dead zone range, the temperature of the reactor loop is adjusted in a delayed mode, and the requirement of automatic reactor power control on load tracking of the steam turbine is met, wherein a control target is controlled by adopting single deviation, the target deviation value is prevented from being artificially expanded, and the frequent action of a power control system is avoided; meanwhile, the power control is quick in response, the temperature control is used as an auxiliary control mode for feedback after the power is adjusted, the control efficiency is high, and large deviation of the temperature of a loop cannot be caused.
Drawings
FIG. 1 is a schematic structural diagram of the present invention.
The system comprises a reactor power measuring module 1, a turbine impulse stage pressure measuring module 2, a primary circuit average temperature measuring module 3, a reactor power output module 4, a turbine power output module 5, a primary circuit reference temperature output module 6, a primary circuit average temperature output module 7, a power deviation data processing module 8, a temperature deviation data processing module 9, a selector module 10, an on-off device 11, a time delay control module 12, a control rod direction and speed logic module 13 and a control rod driving mechanism 14.
Detailed Description
In order to make the technical solutions of the present invention better understood, 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, not all of the embodiments, and are not intended to limit the scope of the present disclosure. Moreover, in the following description, descriptions of well-known structures and techniques are omitted so as to not unnecessarily obscure the concepts of the present disclosure. 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.
There is shown in the drawings a schematic block diagram of a disclosed embodiment in accordance with the invention. The figures are not drawn to scale, wherein certain details are exaggerated and possibly omitted for clarity of presentation. The shapes of various regions, layers and their relative sizes and positional relationships shown in the drawings are merely exemplary, and deviations may occur in practice due to manufacturing tolerances or technical limitations, and a person skilled in the art may additionally design regions/layers having different shapes, sizes, relative positions, according to actual needs.
Referring to fig. 1, the reactor power control system of the invention includes a reactor power measuring module 1, a turbine impulse stage pressure measuring module 2, a primary circuit average temperature measuring module 3, a reactor power output module 4, a turbine power output module 5, a primary circuit reference temperature output module 6, a primary circuit average temperature output module 7, a power deviation data processing module 8, a temperature deviation data processing module 9, a selector module 10, an on-off device 11, a delay control module 12, a control rod direction and speed logic module 13 and a control rod driving mechanism 14;
the output end of the reactor power measuring module 1 is connected with the input end of a reactor power output module 4, the output end of the reactor power output module 4 is connected with the input end of a power deviation data processing module 8, the output end of a turbine impulse stage pressure measuring module 2 is connected with the input end of a turbine power output module 5 and the input end of a primary circuit reference temperature output module 6, the output end of a primary circuit average temperature measuring module 3 is connected with the input end of a primary circuit average temperature output module 7, the output end of the primary circuit reference temperature output module 6 and the output end of the primary circuit average temperature output module 7 are connected with the input end of a selector module 10, the output end of the power deviation data processing module 8 is connected with the input end of the selector module 10 and the input end of a control rod direction and speed logic module 13, and the output end of the selector module 10 is connected with the control end of an on-off device 11, the output end of the temperature deviation data processing module 9 is connected with the input end of the switch 11, the output end of the switch 11 is connected with the input end of the delay control module 12, the output end of the delay control module 12 is connected with the input end of the control rod direction and speed logic module 13, and the output end of the control rod direction and speed logic module 13 is connected with the control end of the control rod driving mechanism 14.
The invention relates to a power control method of a reactor heel machine mode reactor, which comprises the following steps:
1) according to the reactor power output by the reactor power measuring module 1, the reactor real-time power signal P is calculated by the reactor power output module 4 N (ii) a According to the turbine impulse stage pressure output by the turbine impulse stage pressure measuring module 2, a turbine real-time power signal P is calculated by a turbine power output module 5 T ；
2) Calculating reactor power P by means of power deviation data processing module 8 N With turbine power P T The calculated power deviation delta P is input into the selector module 10 and the control rod direction and speed logic module 13;
3) inputting a signal output by the selector module 10 into the on-off device 11 to control the on-off of the on-off device 11, wherein the signal output by the selector module 10 is "0" or "1";
4) when the power deviation delta P is larger than or equal to the preset deviation, the on-off device 11 locks the temperature deviation data processing module 9 to calculate a temperature deviation signal, and when the power deviation delta P exceeds a dead zone value, the control rod direction and speed logic module 13 generates a control rod lifting/inserting instruction and sends the control rod lifting/inserting instruction to the control rod driving mechanism 14, wherein the control rod movement speed is the designed fastest speed, so that the power deviation delta P is lower than the dead zone value;
5) according to the turbine impulse stage pressure output by the turbine impulse stage pressure measuring module 2, a primary circuit coolant reference temperature T is calculated through a primary circuit reference temperature output module 6 ref (ii) a Calculating the average temperature T of the coolant of the primary circuit through a primary circuit average temperature output module 7 according to the average temperature of the primary circuit output by a primary circuit average temperature measuring module 3 avg ；
6) Calculated by the temperature deviation data processing module 9Reference temperature T of primary circuit coolant ref And the average temperature T avg Temperature deviation Δ T of (d);
7) when the power deviation delta P is lower than the preset deviation, the control rod direction and speed logic module 13 does not send a power control signal, the on-off device 11 does not lock the temperature deviation signal generated by the temperature deviation data processing module 9, the control signal generated by the temperature deviation data processing module 9 is delayed by the delay control module 12, and a control rod lifting/inserting instruction is generated by the control rod direction and speed logic module 13 to control the control rod driving mechanism 14 to control the coolant temperature T of the loop avg And adjusting to ensure that the speed of the control rod and the temperature deviation delta T are in a linear relation.
8) At the temperature T of primary circuit coolant avg In the process of regulation, when the power deviation delta P exceeds the limit, the reactor temperature regulation is locked again, and the power deviation data processing module 8, the control rod direction and speed logic module 13 and the control rod driving mechanism 14 restart to regulate the reactor power.
9) And so on until the reference temperature T of the coolant of the reactor primary loop ref And the average temperature T avg Is lower than the dead band value and the reactor power P N With turbine power P T The deviation is lower than the dead zone value, so that the reactor power control can respond in time when the load of the steam turbine changes, and the operation requirement of the reactor following machine is met.

Claims (6)

1. A reactor power control system of a reactor-follower mode is characterized by comprising a reactor power measuring module (1), a turbine impulse stage pressure measuring module (2), a loop average temperature measuring module (3), a reactor power output module (4), a turbine power output module (5), a loop reference temperature output module (6), a loop average temperature output module (7), a power deviation data processing module (8), a temperature deviation data processing module (9), a selector module (10), an on-off device (11), a control rod direction and speed logic module (13) and a control rod driving mechanism (14);
the output end of the reactor power measuring module (1) is connected with the input end of the reactor power output module (4), the output end of the reactor power output module (4) is connected with the input end of the power deviation data processing module (8), the output end of the turbine impulse stage pressure measuring module (2) is connected with the input end of the turbine power output module (5) and the input end of a loop reference temperature output module (6), the output end of a loop average temperature measuring module (3) is connected with the input end of a loop average temperature output module (7), the output ends of the loop reference temperature output module (6) and the loop average temperature output module (7) are connected with the input end of a selector module (10), the output end of the power deviation data processing module (8) is connected with the input end of the selector module (10) and the input end of a control rod direction and speed logic module (13), the output end of the selector module (10) is connected with the control end of the on-off device (11), the output end of the temperature deviation data processing module (9) is connected with the input end of the on-off device (11), the output end of the on-off device (11) is connected with the input end of the control rod direction and speed logic module (13), and the output end of the control rod direction and speed logic module (13) is connected with the control end of the control rod driving mechanism (14).
2. The system of claim 1, wherein the output of the on-off switch (11) is connected to the input of the control rod direction and speed logic module (13) via a delay control module (12).
3. A power control method for a reactor in a reactor-follower mode, which is based on the power control system for a reactor in a reactor-follower mode of claim 1, and comprises the following steps:
1) according to the reactor power output by the reactor power measuring module (1), the reactor real-time power signal P is calculated by the reactor power output module (4) N (ii) a According to the turbine impulse stage pressure output by the turbine impulse stage pressure measuring module (2), a turbine real-time power signal P is calculated through a turbine power output module (5) T ；
2) Calculating the reactor power P by means of a power deviation data processing module (8) N Working with steam turbinesRate P T The calculated power deviation delta P is input into a selector module (10) and a control rod direction and speed logic module (13);
3) inputting a signal output by the selector module (10) into the on-off device (11) to control the on-off of the on-off device (11);
4) when the power deviation delta P is larger than or equal to the preset deviation, the on-off device (11) locks the temperature deviation data processing module (9) to calculate a temperature deviation signal, and when the power deviation delta P exceeds a dead zone value, the control rod direction and speed logic module (13) generates a control rod lifting/inserting instruction, and then controls the control rod driving mechanism (14) so that the power deviation delta P is lower than the dead zone value;
5) according to the turbine impulse stage pressure output by the turbine impulse stage pressure measuring module (2), a primary circuit coolant reference temperature T is calculated through a primary circuit reference temperature output module (6) ref (ii) a Calculating a loop coolant average temperature T by a loop average temperature output module (7) according to a loop average temperature output by a loop average temperature measuring module (3) avg ；
6) Calculating a reference temperature T of the coolant in the circuit by means of a temperature deviation data processing module (9) ref And the average temperature T avg Temperature deviation Δ T of (d);
7) when the power deviation delta P is lower than the preset deviation, the control rod direction and speed logic module 13 does not send out a power control signal, the on-off device (11) does not lock the temperature deviation signal generated by the temperature deviation data processing module (9), and the control signal generated by the temperature deviation data processing module (9) generates a control rod lifting/inserting instruction through the control rod direction and speed logic module (13) to control a control rod driving mechanism (14) and control the temperature T of coolant in a loop avg And (6) carrying out adjustment.
4. The method of claim 3, wherein the signal output by the selector module 10 is 0 or 1.
5. A method for power control in a reactor heel machine mode according to claim 3, characterized in that the output of the on-off switch (11) is connected to the input of the control rod direction and speed logic module (13) via a delay control module (12).
6. The method for controlling the power of the reactor in the reactor-follower mode according to claim 5, wherein in the step 7), the control signal generated by the temperature deviation data processing module (9) is delayed by the delay control module (12), and then a control rod lifting/dropping command is generated by the control rod direction and speed logic module (13).
CN202210577093.9A 2022-05-25 2022-05-25 System and method for controlling power of reactor in pile-follower mode Pending CN114944236A (en)

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CN202210577093.9A CN114944236A (en) 2022-05-25 2022-05-25 System and method for controlling power of reactor in pile-follower mode

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CN202210577093.9A CN114944236A (en) 2022-05-25 2022-05-25 System and method for controlling power of reactor in pile-follower mode

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Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO2024125302A1 (en) * 2022-12-12 2024-06-20 中广核研究院有限公司 Reactor control method and apparatus, computer device and storage medium

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO2024125302A1 (en) * 2022-12-12 2024-06-20 中广核研究院有限公司 Reactor control method and apparatus, computer device and storage medium

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