CN111462925B - Nuclear reactor power adjusting method and system based on operation data - Google Patents
Nuclear reactor power adjusting method and system based on operation data Download PDFInfo
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- CN111462925B CN111462925B CN202010307630.9A CN202010307630A CN111462925B CN 111462925 B CN111462925 B CN 111462925B CN 202010307630 A CN202010307630 A CN 202010307630A CN 111462925 B CN111462925 B CN 111462925B
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C7/00—Control of nuclear reaction
- G21C7/06—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
- G21C7/08—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section by displacement of solid control elements, e.g. control rods
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C7/00—Control of nuclear reaction
- G21C7/06—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
- G21C7/08—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section by displacement of solid control elements, e.g. control rods
- G21C7/12—Means for moving control elements to desired position
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Abstract
The invention discloses a nuclear reactor power regulation method and a nuclear reactor power regulation system based on operation data, wherein a database is established by utilizing the relation between the nuclear reactor state quantity and the rod position of a control rod generated in the operation process of the nuclear reactor, the database is inquired in advance in load regulation to obtain the target rod position of the control rod, the coarse regulation and fine regulation combined strategy is adopted, the coarse regulation and fine regulation output signals in the power regulation system are weighted and added to be used as the output signals of the power regulation system, and the moving direction and speed of the control rod are controlled by the output signals to realize the nuclear reactor power regulation. The invention improves the control performance, reduces the overshoot and the adjusting time, has the self-adaptability and effectively prolongs the service life of the control rod.
Description
Technical Field
The invention belongs to the technical field of nuclear reactor control, and particularly relates to a nuclear reactor power adjusting method and a nuclear reactor power adjusting system based on operation data.
Background
The control of nuclear reactor power is achieved by varying the reactivity, which is regulated in a number of ways, most commonly by means of movable control rods containing a strong neutron absorbing substance, which are inserted or withdrawn to vary the amount of neutron absorbed in the reactor and thus the reactivity and the nuclear reactor power. The movement of the control rods is accomplished by means of a control rod drive mechanism, which is a mechanical device that, if the control rods are over-tuned during power adjustment, increases the stroke of the control rods, causing excessive use of the mechanical device, resulting in a reduction in its life. Particularly, in a nuclear power plant, the power of a nuclear reactor needs to be frequently adjusted to adapt to different working condition changes, and the use frequency of a control rod driving mechanism is increased, so that the requirement for reducing the overshoot of a control rod in the load change process is more outstanding.
The existing nuclear reactor power regulating system is based on a traditional proportional-integral-derivative (PID) controller and comprises a feed-forward control channel with power mismatch and a feedback control channel of average coolant temperature, wherein an input signal of the feed-forward control channel with power mismatch is a deviation between a load set value and a nuclear reactor power measured value, so that the nuclear reactor power can quickly respond to the change of system load; the feedback control channel input of the average temperature of the coolant is the deviation between the set value and the measured value of the average temperature of the coolant, so that the imbalance between the power and the load of the reactor can be adjusted more finely. The algebraic sum of the output signals of the two control channels drives the control rod drive, determining the control rod lift or drop, and the rate of movement, ultimately eliminating the offset.
When the load is reduced, the load change of the two loops is quick in response and can reach the vicinity of a target load value quickly, the reactor power is reduced along with the load reduction but is slower in response than the change of the load of the two loops, and the power value is higher than the load value in the initial period of time. Also, since the average coolant temperature responds more slowly, the deviation of the average coolant temperature will always be positive when the measured average coolant temperature is higher than the set point. During the load reduction process, when the control rod reaches the target rod position, the measured value of the average temperature of the coolant is higher than the set value of the temperature due to the fact that the measured value of the power is higher than the set value. At this time, the power mismatch deviation and the coolant average temperature deviation drive the control rods to continue to be inserted, so that the control rods are inserted to a lower position first and then adjusted back to the rod position corresponding to the target load, resulting in a large overshoot. There is a large overshoot and settling time of the control rods during load leveling.
The traditional feedback control method does not fully utilize the system characteristics of the operation of the nuclear reactor and a large amount of data generated in the operation process, and the problems of overlarge overshoot, long adjustment time and the like can occur in the actual adjustment process.
Disclosure of Invention
The technical problem to be solved by the present invention is to provide a nuclear reactor power adjusting method and system based on operation data, in order to overcome the defects in the prior art, in the operation process, important parameters representing the state of the nuclear reactor and the rod position of a control rod under different load levels are recorded, a database is manufactured, in the load adjusting process, the rod position of the control rod corresponding to a target load value is obtained in advance by inquiring the database, and by optimizing the power adjusting process, the overshoot and the adjusting time of the control rod are reduced, and the service life of the control rod is prolonged.
The invention adopts the following technical scheme:
a nuclear reactor power regulation method based on operation data is characterized in that a database is established by utilizing the relation between the nuclear reactor state quantity and the rod position of a control rod generated in the operation process of a nuclear reactor, the database is inquired in advance in load regulation to obtain the target rod position of the control rod, the coarse regulation output signal and the fine regulation output signal in a power regulation system are weighted and added to serve as the output signal of the power regulation system, and the moving direction and the moving speed of the control rod are controlled through the output signal to realize the nuclear reactor power regulation.
Specifically, when the distance between the control rod and the target rod position is greater than 80% of the absolute value of the deviation between the rod position before adjustment and the target rod position, the coarse adjustment stage is adopted, and the rod position deviation of the control rod is used as a driving signal through feedforward control to enable the control rod to move towards the target rod position; when the distance between the control rod and the target rod position is less than 25% of the absolute value of the deviation between the rod position before adjustment and the target rod position, the fine adjustment stage is adopted, and the average temperature deviation and the power-load deviation of the coolant are used as driving signals through feedback control to reduce the steady-state deviation; and setting the transition stage in the process of the coarse adjustment to fine adjustment transition, and realizing the smooth transition of the two stages through the coarse adjustment weight coefficient and the fine adjustment weight coefficient.
Further, let A be the half length of the coarse adjustment interval, which represents 80% of the absolute value of the deviation between the pre-adjustment rod position and the target rod position, B be the half length of the fine adjustment interval, which represents less than 25% of the absolute value of the deviation between the pre-adjustment rod position and the target rod position, in the coarse adjustment stage, the absolute value of the rod position deviation is greater than A, the weighting coefficient of the coarse adjustment output signal is 1, and the weighting coefficient of the fine adjustment output signal is 0; in the fine adjustment stage, the absolute value of the rod position deviation is smaller than B, the weighting coefficient of the coarse adjustment output signal is 0, and the weighting coefficient of the fine adjustment output signal is 1; in the transition stage, the absolute value of the rod position deviation is greater than B and smaller than A, and the sum of the weighting coefficients of the coarse adjustment output signal and the fine adjustment output signal is 1; A. b, the weighting coefficients of the coarse adjustment output signals and the fine adjustment output signals in the transition stage are determined by the load lifting speed, and when the load change speed is less than 1% of full load per second, A is kept unchanged; on the contrary, when the load change rate is more than or equal to 1% of the full load per second, the proportion occupied by coarse adjustment is increased, namely A is adjusted to 75% of the absolute value of the deviation between the rod position before adjustment and the target rod position.
Specifically, when the control rod approaches the target rod position, the specific gravity of the fine adjustment signal is gradually increased from 0 to 100 percent; when the control rod is far away from the target rod position, the specific gravity of the coarse adjustment signal is gradually increased from 0 to 100 percent, so that the control rod moves towards the target rod position.
Specifically, when the nuclear power plant operates in a stable state, variables related to power regulation and variables reflecting the reactor state are recorded, and a corresponding relation between the control rod position and the variables related to power regulation and the variable data reflecting the reactor state is established according to the variables related to power regulation and the variable data reflecting the reactor state.
Further, variables related to power regulation and reflecting reactor status include coolant average temperature, coolant flow, reactor power, turbine load, burn-up depth/current time, and control rod position.
Specifically, after the database is established, the data exceeding 2 months is removed by using fading memory, and the weight of the data within one week from the current operation time is increased.
Specifically, the input of the power regulating system module is a load set value, a lifting load rate, a control rod target rod position, reactor power and coolant average temperature; the output is the moving speed and direction of the control rod, when the operator determines the set load value and the lifting load rate, the database inquires to obtain the target rod position of the control rod, and the lifting load rate adjusts the transition interval and the weight coefficient of the coarse adjustment and the fine adjustment.
The other technical scheme of the invention is that the power regulating system comprises a load set value and lifting load rate module, a power regulating module and a database module; the load set value and the lifting load rate module are input by an operator and then are sent to the database module and the power regulation module; the database module is used for establishing the relation among the average temperature of the coolant, the flow rate of the coolant, the reactor power, the load of the steam turbine, the burnup depth/current time and the rod position of the control rod, inquiring and obtaining the target rod position of the control rod according to a load set value, and the power adjusting module adjusts the rod speed and the rod position of the control rod of the nuclear reactor after receiving the target rod position information of the control rod.
Compared with the prior art, the invention has at least the following beneficial effects:
the nuclear reactor power regulation method based on the operation data fully utilizes the operation data of the nuclear reactor, establishes the relation between the control rod position and the working condition of the reactor, considers the factors of the average temperature of the coolant, the flow of the coolant and the like reflecting the state of the reactor, provides the accurate control rod target position for a power regulation system, and improves the control performance; when the load changes, the target rod position of the control rod is known in advance, so that a foundation is established for setting coarse adjustment and fine adjustment, and the overshoot and the adjustment time are reduced; the connection between the coarse adjustment transition interval and the fine adjustment transition interval and the connection between the weight coefficient and the load change rate are established, so that the power adjusting system can automatically adapt to the requirement of load change and has self-adaptability.
Further, the typical process of power regulation is divided into three stages of coarse regulation, transition and fine regulation according to the deviation of the rod position and the target rod position. The set weighting function enables the proportion of coarse adjustment and fine adjustment of the rod control signal to be different in the three stages, so that the control rod can rapidly move to the target rod position when the rod position deviation is large, and the deviation is adjusted finely after the distance is close.
Furthermore, a weighting function which changes along with the rod position is designed, target rod position information obtained by utilizing operation data in the initial stage of adjustment can be utilized, feedback adjustment can be carried out according to temperature and power in the final stage of adjustment, and meanwhile, sudden change of a control signal cannot occur in the whole process.
Furthermore, aiming at the characteristics of different power levels of the reactor, different weighting coefficient functions are adopted in different working conditions, and different rough adjustment proportions are set, so that the designed power adjustment method has better adaptability, and the control performance in various working conditions can be improved.
Further, in long-term operation, the dynamic characteristics, reactivity value distribution, and other attributes of the reactor may change over time. By establishing and updating the reactor operation database, the target rod position deviation generated by the long-term change effect of the reactor can be reduced, and the adaptability of the power regulation system is improved.
Furthermore, in the adjusting system, data with reference value in the database is extracted for calculating the target rod position by a fading memory method, so that the operation speed can be improved, effective data can be fully utilized, and the deviation of the target rod position is reduced.
The invention also discloses a power regulating system, which utilizes a large amount of data generated in the reactor operation process to establish the relationship between the control rod position and each operation parameter. In the adjusting process, the target rod position of the control rod is determined according to reactor parameters and the load of the steam turbine, the control rod is quickly adjusted to be close to the target rod position by using a mode of combining coarse adjustment and fine adjustment, and deviation is eliminated by using feedback adjustment, so that the stroke of the control rod is shortened, and the load tracking performance of the reactor is improved.
In conclusion, the invention improves the control performance, reduces the overshoot and the adjusting time, has self-adaptability and effectively prolongs the service life of the control rod.
The technical solution of the present invention is further described in detail by the accompanying drawings and embodiments.
Drawings
FIG. 1 is a schematic diagram of a typical pressurized water reactor nuclear power plant;
FIG. 2 illustrates a nuclear reactor power regulation database construction principle;
FIG. 3 is a schematic diagram of a new method of nuclear reactor power regulation;
FIG. 4 is a schematic diagram of a fine tuning principle in nuclear reactor power conditioning;
FIG. 5 is a schematic diagram of a coarse tuning principle in nuclear reactor power regulation;
FIG. 6 is a schematic diagram of coarse and fine weighting coefficients for nuclear reactor power control;
FIG. 7 is a graph showing the effect of the new method for linear load reduction at 1% full load per second, wherein (a) is the control rod position response and (b) is the reactor power response;
FIG. 8 is a graph showing the effect of the new method for linear load reduction at 2% full load per second, wherein (a) is the control rod position response and (b) is the reactor power response.
Detailed Description
Referring to fig. 1, a pressurized water reactor nuclear power plant has two loops, a steam generator 1 is a heat transfer device between the two loops, coolant flows in one loop to take away heat generated in a reactor core of a reactor 2, a control rod 3 controls power of the reactor, and a voltage stabilizer 4 stabilizes the pressure; the feed water in the two circuits absorbs the heat of the coolant, and the steam is generated through a main steam pipeline 5 and sent to a steam turbine to finally generate electric energy. During the operation of the pressurized water reactor, a measurement quantity reflecting the state of the reactor is obtained, and the measurement quantity reflecting the state of the reactor is recorded through an instrument control system of the nuclear power plant.
The invention provides a nuclear reactor power regulation method based on operation data, which is characterized in that a database is established based on the relation between the quantity reflecting the state of a nuclear reactor and the rod position of a control rod generated in the operation process of the nuclear reactor, the database is inquired in advance in load regulation to obtain a target rod position, a power regulation system adopts a strategy combining coarse regulation and fine regulation, and when the distance between the control rod and the target rod position is greater than 80% of the absolute value of the deviation between the rod position before regulation and the target rod position, the control rod moves to the target rod position at a certain speed through feed-forward control in a coarse regulation stage; when the distance between the control rod and the target rod position is less than 25% of the absolute value of the deviation between the rod position before adjustment and the target rod position, the fine adjustment stage is performed, and the steady state deviation is reduced through feedback control; setting a transition stage in the process of changing from coarse adjustment to fine adjustment, realizing stable transition between the two stages through proper coarse adjustment and fine adjustment weight coefficients, and enabling the power regulation system to automatically adapt to the requirement of load change rate, wherein the settings of the transition stage and the weight system are related to the load lifting rate; if the control rod is close to the target rod position, the fine adjustment proportion is increased, the control precision is improved, and the overshoot is reduced; if the control rod is far away from the target rod position, the coarse tuning specific gravity is increased, so that the control rod moves to the target rod position as soon as possible, the response speed is improved, and the problems of large overshoot and long adjusting time of the traditional nuclear reactor power adjusting system are solved.
The invention relates to a nuclear reactor power regulation method based on operation data, which comprises the following steps:
s1, adopting the variable related to power adjustment and the variable reflecting the reactor state to construct a database, and accurately inquiring and obtaining the target rod position of the control rod in different load levels;
the variables associated with power regulation and reflecting reactor conditions are specifically as follows:
coolant average temperature, coolant flow, reactor power, turbine load, burn-up depth/current time, and control rod position.
Referring to fig. 2, when the nuclear power plant is operating in a steady state, variables related to power regulation and reflecting the reactor state are recorded, and a corresponding relationship between the position of the control rod and the variables is established according to the data.
S2, processing the data of different operation times in the database established in the step S1 by using the weight coefficient, wherein the weight of the data of the current operation time is larger, so that the influence caused by the change of the burnup depth, the control rod value and the like in the operation process of the nuclear reactor is reduced;
along with the operation of the nuclear reactor, the database is continuously updated, the reactor power, the steam turbine load, the loop coolant temperature, the loop coolant flow, the steam generator feed water flow and the operation time are used as independent variables, the final rod position of the control rod is used as a dependent variable, the weight close to the current operation time data is increased, the query speed is increased, the accurate rod position of the control rod under a certain target working condition can be rapidly queried by using the database, and a foundation is established for power regulation.
And S3, performing coarse adjustment and fine adjustment on the power regulation system by using the database processed in the step S2, weighting and adding output signals of the coarse adjustment and the fine adjustment to obtain an output signal of the power regulation system, and controlling the movement direction and the speed of a control rod through the output signal to realize the nuclear reactor power regulation system based on the operation data.
Referring to fig. 3, the power regulation system includes a load set point and hoist load rate module 6, a power regulation system module 7, and a database module 8. The load set value and the lifting load rate module 6 are input by an operator; the database module 8 establishes the relation between the rod position of the control rod and variables such as load and the like, and inquires and obtains the target rod position of the control rod according to the load set value; the input of the power regulating system module 7 is a load set value, a lifting load rate, a control rod target rod position, reactor power, coolant average temperature and the like; the output is the speed and direction of movement of the control rods.
After the operator determines the load set value and the lifting load rate, the database is inquired to obtain the target rod position of the control rod, the lifting load rate is used for adjusting the transition interval and the weight coefficient of coarse adjustment and fine adjustment, and the rod speed and the rod position of the control rod are adjusted through the power adjusting system module, so that power adjustment is finally realized.
Referring to fig. 4, the fine tuning section retains the conventional power adjusting system, i.e., the reactor power is finely adjusted by the deviation of the average temperature of the coolant in response to the rapid response upon occurrence of the power load mismatch, and outputs the control rod speed required for the fine tuning section.
Referring to fig. 5, with the feedforward control, the stick position deviation is used as the input of the controller, the output signal is the control stick speed required by the coarse adjustment part, the controller is a nonlinear link, and when the absolute value of the stick position deviation is lower than the dead zone, the output signal is 0; when the absolute value of the deviation is larger than the dead zone value, the output signal is the highest rod speed, and the direction is consistent with the positive and negative of the deviation.
In the actual design aiming at a specific object, controllers of a coarse adjusting part and a fine adjusting part can be changed according to specific conditions, the coarse adjusting part can change a dead zone according to the characteristics of an actual stack, and the fine adjusting part can adjust parameters according to steady-state errors, anti-interference capacity and the like.
Referring to fig. 6, the method for determining the weighting coefficients of the coarse and fine adjustment output signals includes: let A be the half length of the coarse adjustment interval, which represents 80% of the absolute value of the deviation between the pre-adjustment position and the target position, and B be the half length of the fine adjustment interval, which represents less than 25% of the absolute value of the deviation between the pre-adjustment position and the target position.
When the absolute value of the rod position deviation is greater than A, the weighting coefficient of the coarse adjustment output signal is 1, the weighting coefficient of the fine adjustment output signal is 0, the stage is a coarse adjustment stage, and the control rod moves to the target rod position at a certain speed;
when the absolute value of the rod position deviation is smaller than B, the weighting coefficient of the coarse adjustment output signal is 0, the weighting coefficient of the fine adjustment output signal is 1, and the stage is a fine adjustment stage;
when the absolute value of the rod position deviation is larger than B and smaller than A, the sum of the weighting coefficients of the coarse adjustment output signal and the fine adjustment output signal is 1 in the transition stage.
A, B, and the weighting coefficients of the coarse and fine output signals in the transition stage are determined by the load lifting speed, and A is kept unchanged when the load change speed is less than 1% of full load per second; on the contrary, when the load change rate is more than or equal to 1% of the full load per second, the proportion occupied by coarse adjustment is increased, namely A is adjusted to 75% of the absolute value of the deviation between the rod position before adjustment and the target rod position.
In order to make the objects, technical solutions and advantages of the embodiments of the present invention clearer, 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 some, but not all, embodiments of the present invention. The components of the embodiments of the present invention generally described and illustrated in the figures herein may be arranged and designed in a wide variety of different configurations. Thus, the following detailed description of the embodiments of the present invention, presented in the figures, is not intended to limit the scope of the invention, as claimed, but is merely representative of selected embodiments of the invention. 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.
Referring to FIG. 7, a system response curve for load shedding regulation in a PWR nuclear power plant using a power regulation system employing both the new and the conventional methods is shown. In fig. 7, the load set point is for a drop from 100% full load to 10% full load at a rate of 1% full load per second, with a and B taking the values of 8cm and 5cm, respectively. As can be seen from fig. 7(a), the overshoot of the control rod using the present invention is 10.4%, while the overshoot of the control rod in the conventional method is 55.1%. As can be seen from fig. 7(b), the reactor power was adjusted for 263 seconds using the present invention and 313 seconds using the conventional method. Therefore, the overshoot of the control rod is obviously reduced by adopting the invention, and the regulation time of the reactor power is also obviously shortened.
Referring to fig. 8, the load set point is from 100% full load to 10% full load at a rate of 2% full load per second, with a and B taking the values of 20cm and 5cm, respectively. As can be seen from fig. 8(a), the overshoot of the control rod using the present invention is 27.7%, while the overshoot of the control rod in the conventional method is 70.2%. As can be seen from fig. 8(b), the reactor power was adjusted for 254 seconds using the present invention and 327 seconds using the conventional method.
The invention uses the operation data of the nuclear reactor to establish a database of the relationship between the control rod position and the variables related to the operation state of the nuclear reactor, wherein the variables reflecting the operation state of the nuclear reactor comprise reactor power, load, average temperature of coolant, flow rate of coolant, burnup depth and the like, wherein the burnup depth is a measure of the fuel consumption of the nuclear reactor, and can be characterized by the operation time of the nuclear reactor. By using the database, the control rod position corresponding to the load set value in the load adjustment process can be obtained and used as the control rod target position for nuclear reactor power adjustment.
A control method combining coarse adjustment and fine adjustment is arranged in a nuclear reactor power regulation system, wherein the coarse adjustment adopts feed-forward control, and the response speed is improved. In the initial stage of load change, the control rod position is far away from the target rod position, and the control rod is quickly moved to the target rod position by adopting a coarse adjustment method. When the control rod is close to the target rod position, a fine adjustment method is adopted to reduce the moving distance and the overshoot of the control rod. And setting the weight coefficients of the coarse adjustment and the fine adjustment in the transition interval from the coarse adjustment to the fine adjustment to enable the smooth transition from the coarse adjustment to the fine adjustment.
The selection of the transition interval and the weighting factor depends on the rate at which the load is lifted. If the load change rate is faster, the transition interval needs to be reduced, the weight of coarse adjustment is increased, the movement of the control rod is guided by the coarse adjustment as much as possible, and the rapid movement adapts to the requirement of rapid load change. If the load change rate is slower, the fine adjustment effect needs to be increased, and the overshoot and the steady-state error are reduced.
The above-mentioned contents are only for illustrating the technical idea of the present invention, and the protection scope of the present invention is not limited thereby, and any modification made on the basis of the technical idea of the present invention falls within the protection scope of the claims of the present invention.
Claims (6)
1. A nuclear reactor power regulation method based on operation data is characterized in that a database is established by utilizing the relation between the nuclear reactor state quantity and the rod position of a control rod generated in the operation process of a nuclear reactor, the database is inquired in advance in load regulation to obtain the target rod position of the control rod, the coarse regulation and fine regulation output signals in a power regulation system are weighted and added to serve as the output signals of the power regulation system by adopting a strategy of combining coarse regulation and fine regulation, and the moving direction and the speed of the control rod are controlled by the output signals to realize the nuclear reactor power regulation;
when the distance between the control rod and the target rod position is greater than 80% of the absolute value of the deviation between the rod position before adjustment and the target rod position, the coarse adjustment stage is performed, and the control rod is moved to the target rod position by taking the rod position deviation of the control rod as a driving signal through feedforward control; when the distance between the control rod and the target rod position is less than 25% of the absolute value of the deviation between the rod position before adjustment and the target rod position, the fine adjustment stage is adopted, and the average temperature deviation and the power-load deviation of the coolant are used as driving signals through feedback control to reduce the steady-state deviation; setting a transition stage in the process of converting from coarse adjustment to fine adjustment, realizing the stable transition of two stages through coarse adjustment and fine adjustment weight coefficients, setting A as the half length of a coarse adjustment interval to represent 80% of the absolute value of the deviation between the rod position before adjustment and a target rod position, setting B as the half length of a fine adjustment interval to represent less than 25% of the absolute value of the deviation between the rod position before adjustment and the target rod position, wherein in the coarse adjustment stage, the absolute value of the rod position deviation is greater than A, the weighting coefficient of a coarse adjustment output signal is 1, and the weighting coefficient of a fine adjustment output signal is 0; in the fine adjustment stage, the absolute value of the rod position deviation is smaller than B, the weighting coefficient of the coarse adjustment output signal is 0, and the weighting coefficient of the fine adjustment output signal is 1; in the transition stage, the absolute value of the rod position deviation is greater than B and smaller than A, and the sum of the weighting coefficients of the coarse adjustment output signal and the fine adjustment output signal is 1; A. b, the weighting coefficients of the coarse adjustment output signals and the fine adjustment output signals in the transition stage are determined by the load lifting speed, and when the load change speed is less than 1% of full load per second, A is kept unchanged; on the contrary, when the load change rate is more than or equal to 1 percent of the full load per second, the proportion occupied by coarse adjustment is increased, namely A is adjusted to be 75 percent of the absolute value of the deviation between the rod position before adjustment and the target rod position;
when the nuclear power plant operates in a stable state, recording variables related to power regulation and variables reflecting the state of the reactor, and establishing a corresponding relation between the position of the control rod and the variables related to power regulation and the variable data reflecting the state of the reactor according to the variables related to power regulation and the variable data reflecting the state of the reactor.
2. The nuclear reactor power regulation method based on operational data of claim 1, wherein the proportion of the fine adjustment signal is increased gradually from 0 to 100% when the control rod approaches the target rod position; when the control rod is far away from the target rod position, the specific gravity of the coarse adjustment signal is gradually increased from 0 to 100 percent, so that the control rod moves towards the target rod position.
3. A method for nuclear reactor power conditioning based on operational data as claimed in claim 1 wherein variables related to power conditioning and reflecting reactor status include coolant average temperature, coolant flow, reactor power, turbine load, burn-up depth/current time and control rod position.
4. A method for regulating power in a nuclear reactor based on operating data as claimed in claim 1, in which the database is created and then erased using progressive memory, removing more than 2 months of data and weighting the data up to one week of current operating time.
5. The method of claim 1, wherein the inputs to the power management system module are a load set point and a lift load rate, a control rod target position, a reactor power, and a coolant average temperature; the output is the moving speed and direction of the control rod, when the operator determines the set load value and the lifting load rate, the database inquires to obtain the target rod position of the control rod, and the lifting load rate adjusts the transition interval and the weight coefficient of the coarse adjustment and the fine adjustment.
6. A power regulation system for a regulation method according to claim 1, characterized in that the power regulation system comprises a load set point and hoisting load rate module, a power regulation module and a database module; the load set value and the lifting load rate module are input by an operator and then are sent to the database module and the power regulation module; the database module is used for establishing the relation among the average temperature of the coolant, the flow rate of the coolant, the reactor power, the load of the steam turbine, the burnup depth/current time and the rod position of the control rod, inquiring and obtaining the target rod position of the control rod according to a load set value, and the power adjusting module adjusts the rod speed and the rod position of the control rod of the nuclear reactor after receiving the target rod position information of the control rod.
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| Application Number | Priority Date | Filing Date | Title |
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| CN202010307630.9A CN111462925B (en) | 2020-04-17 | 2020-04-17 | Nuclear reactor power adjusting method and system based on operation data |
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| CN202010307630.9A CN111462925B (en) | 2020-04-17 | 2020-04-17 | Nuclear reactor power adjusting method and system based on operation data |
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