CN116627025A - Simulation method and device of high-temperature gas cooled reactor nuclear power control system - Google Patents
Simulation method and device of high-temperature gas cooled reactor nuclear power control system Download PDFInfo
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Abstract
The embodiment of the disclosure provides a simulation method and device of a high-temperature gas cooled reactor nuclear power control system, wherein the method comprises the following steps: differentiating the core power controller and applying a negative reactive perturbation to the core power controller; obtaining a closed loop dynamic response curve of each process state variable of the nuclear power control system under the differential action; selecting a target differential time constant according to a closed loop dynamic response curve under the differential action; performing differential action and proportional action on the nuclear power controller respectively, applying a disturbance signal of a nuclear power set value to the nuclear power controller, and selecting a differential time constant as a target differential time constant; obtaining a closed loop dynamic response curve under differential action and proportional action; the target proportional gain is selected based on the closed loop dynamic response curve under differential and proportional action. The method can simulate and verify the regulation characteristic of the full-plant power automatic control and regulation system control nuclear power control system in advance, and avoid frequent disturbance to the unit during actual application of engineering.
Description
Technical Field
The embodiment of the disclosure belongs to the technical field of automatic control of high-temperature gas cooled reactors, and particularly relates to a simulation method and device of a high-temperature gas cooled reactor nuclear power control system.
Background
The nuclear power control system is used for first application of domestic nuclear power plants in China, explores and formulates a perfect debugging method and strategy, adopts a feasible simulation verification test, verifies the rationality of a debugging method of key system equipment of a high-temperature gas cooled reactor demonstration project and the reliability of the system equipment, grasps the debugging method of the key system equipment and the operation characteristics of the key system equipment, satisfactorily completes the debugging task of the high-temperature reactor demonstration project, ensures the safe and reliable operation of the high-temperature reactor demonstration project, promotes the commercialization of a booster high-temperature reactor, and lays a solid foundation for the high-temperature gas cooled reactor with completely independent intellectual property rights to the world.
Because the high-temperature gas cooled reactor demonstration project is a multi-input multi-output complex large system, a close coupling relation exists between each control quantity and the regulated quantity, and aiming at the complex characteristic of the control process, a control strategy is based on a large system hierarchical control theory, so that a coordination control system with a power distribution control layer, a coordination control layer and a local control side three-layer hierarchical control structure is formed, the coordination control strategy to an executing mechanism is applied to engineering practice for the first time, and the debugging work of a nuclear power control system is a totally new challenge.
In view of the above problems, it is necessary to provide a simulation method and a simulation device for a high-temperature gas cooled reactor nuclear power control system which are reasonable in design and effectively solve the above problems.
Disclosure of Invention
The embodiment of the disclosure aims at least solving one of the technical problems existing in the prior art and provides a simulation method and a simulation device of a high-temperature gas cooled reactor nuclear power control system.
An aspect of an embodiment of the present disclosure provides a simulation method of a high temperature gas cooled reactor nuclear power control system, the method including:
performing differential action on a nuclear power controller, and applying negative reactive disturbance with the amplitude range of-15 pcm to-5 pcm to the nuclear power controller;
according to the negative reactive disturbance, a closed-loop dynamic response curve of each process state variable of the nuclear power control system under the differential action under different differential time constants is obtained;
selecting a target differential time constant according to the closed loop dynamic response curve under the differential action under different differential time constants;
performing differential action and proportional action on the core power controller respectively, and applying a negative/positive step disturbance signal with a core power set value in an amplitude range of 0.1% -0.5% to the core power controller, wherein the differential time constant of the core power controller is the target differential time constant;
obtaining closed loop dynamic response curves of all process state variables of the nuclear power control system under differential action and proportional action under different proportional gains according to the negative/positive step disturbance signals of the nuclear power set value;
the target proportional gain is selected based on the closed loop dynamic response curves under differential action and proportional action described under different proportional gains.
Optionally, the obtaining a closed-loop dynamic response curve of each process state variable of the nuclear power control system under differential action under different differential time constants according to the negative reactive disturbance includes:
and according to the negative reactive disturbance, adjusting a differential time constant of the nuclear power controller to obtain a closed-loop dynamic response curve of each process state variable of the nuclear power control system from the initial state to the steady state under different differential time constants so as to obtain the closed-loop dynamic response curve of the nuclear power control system under the differential action.
Optionally, said adjusting a differential time constant of said core power controller includes:
the differential time constant of the core power controller is adjusted to be in the range of 0.5-5.
Optionally, the selecting a target differential time constant according to the closed loop dynamic response curve under differential action under different differential time constants includes:
the target differential time constant is selected from among different differential time constants according to at least one of the oscillation magnitude, the short settling time and the deviation magnitude of the closed-loop dynamic response curve under differential action.
Optionally, the applying a negative reactive disturbance with a magnitude ranging from-15 pcm to-5 pcm to the core power controller includes:
inserting the compensation rod at maximum speed introduces a negative reactive disturbance with an amplitude ranging from-15 to-5 pcm.
Optionally, the obtaining a closed loop dynamic response curve of each process state variable of the core power control system under differential action and proportional action according to the negative/positive step disturbance signal of the core power set value under different proportional gains includes:
and adjusting the proportional gain of the nuclear power controller according to the negative/positive step disturbance signal of the nuclear power set value to obtain a closed-loop dynamic response curve from the initial state to the steady state of each process state variable of the nuclear power control system under different proportional gains so as to obtain the closed-loop dynamic response curve of the nuclear power control system under the differential action and the proportional action.
Optionally, the adjusting the proportional gain of the core power controller includes:
setting the proportional gain to a smaller value and gradually increasing the proportional gain; wherein the adjustment range of the proportional gain is 0.2-10.
Optionally, the selecting a target proportional gain according to the closed loop dynamic response curve under the differential action and the proportional action includes:
the target proportional gain is selected from among the different proportional gains according to at least one of oscillation magnitude, short settling time, and deviation magnitude of the closed-loop dynamic response curve under differential action and proportional action.
Optionally, the process state variables include at least one of control rod actuator drive signals, control rod positions, nuclear power, reactor outlet hot helium temperature, evaporator outlet vapor temperature, and output thermal power.
Another aspect of the disclosed embodiments provides a simulation apparatus of a high temperature gas cooled reactor nuclear power control system, the apparatus comprising:
the first setting module is used for differentiating the nuclear power controller and applying negative reactive disturbance with the amplitude range of-15 pcm to-5 pcm to the nuclear power controller;
the first response curve acquisition module is used for acquiring a closed-loop dynamic response curve of each process state variable of the nuclear power control system under the differential action under different differential time constants according to the negative reactive disturbance;
the first selection module is used for selecting a target differential time constant according to the closed-loop dynamic response curve under the differential action under different differential time constants;
the second setting module is used for respectively performing differential action and proportional action on the nuclear power controller and applying a negative/positive step disturbance signal with a nuclear power set value in an amplitude range of 0.1% -0.5% to the nuclear power controller, wherein the differential time constant of the nuclear power controller is the target differential time constant;
the second response curve acquisition module is used for acquiring a closed-loop dynamic response curve of each process state variable of the nuclear power control system under the differential action and the proportional action under different proportional gains according to the negative/positive step disturbance signal of the nuclear power set value;
and the second selection module is used for selecting a target proportional gain according to the closed loop dynamic response curves under the differential action and the proportional action under different proportional gains.
According to the simulation method and the simulation device for the high-temperature gas cooled reactor nuclear power control system, in the debugging process of the nuclear power controller, the target differential time constant and the target proportional gain are obtained according to the closed-loop dynamic response curve of each process state variable of the nuclear power control system, and the accurate control of the nuclear power is realized in actual operation through the target differential time constant and the target proportional gain. According to the embodiment of the disclosure, the regulation characteristics of the full-plant power automatic control and regulation system control nuclear power control system can be verified in advance through simulation, so that frequent disturbance for a unit during actual application of engineering is avoided, and the high-temperature gas cooled reactor can be operated safely and reliably according to a debugging result.
Drawings
FIG. 1 is a schematic diagram of a working flow of a nuclear power controller of a nuclear power control system of a high temperature gas cooled reactor according to an embodiment of the disclosure;
FIG. 2 is a schematic flow chart of a simulation method of a nuclear power control system of a high temperature gas cooled reactor according to another embodiment of the disclosure;
FIG. 3 is a simulation curve of a driving signal of a control rod driving mechanism under the differential action of a closed loop test of a nuclear power control system of a simulation method of a nuclear power control system of a high temperature gas cooled reactor in another embodiment of the disclosure;
FIG. 4 is a graph of a simulation of nuclear power under the action of a closed loop test differential of a nuclear power control system of a simulation method of a nuclear power control system of a high temperature gas cooled reactor in another embodiment of the disclosure;
FIG. 5 is a graph of a simulation of reactor outlet helium temperature under the differential action of a closed loop test of a nuclear power control system of a simulation method of a nuclear power control system of a high temperature gas cooled reactor in another embodiment of the disclosure;
FIG. 6 is a graph of simulation of evaporator outlet steam temperature under the differential action of a closed loop test of a nuclear power control system of a simulation method of a nuclear power control system of a high temperature gas cooled reactor in another embodiment of the disclosure;
FIG. 7 is a graph showing a simulation of the output thermal power of a nuclear power control system according to a method for simulating the nuclear power of a high temperature gas cooled reactor according to another embodiment of the present disclosure;
FIG. 8 is a simulation plot of a control rod actuator drive signal for a nuclear power control system in accordance with a method for simulating a nuclear power control system of a high temperature gas cooled reactor in accordance with an alternative embodiment of the present disclosure;
FIG. 9 is a graph of a simulation of nuclear power in a closed loop test of a nuclear power control system of a simulation method of a nuclear power control system of a high temperature gas cooled reactor in accordance with another embodiment of the present disclosure;
FIG. 10 is a graph of a simulation of reactor outlet hot helium temperature under the proportional and differential effects of a closed loop test of a nuclear power control system of a simulation method of a nuclear power control system of a high temperature gas cooled reactor in accordance with another embodiment of the present disclosure;
FIG. 11 is a graph of simulation of evaporator outlet steam temperature under proportional and differential closed loop test of a nuclear power control system of a simulation method of a nuclear power control system of a high temperature gas cooled reactor in accordance with another embodiment of the present disclosure;
FIG. 12 is a graph showing a simulation of the output thermal power of a nuclear power control system of a simulation method of a nuclear power control system of a high temperature gas cooled reactor according to another embodiment of the present disclosure under the proportional action and differential action of a closed loop test;
fig. 13 is a schematic structural diagram of a simulation device of a nuclear power control system of a high-temperature gas cooled reactor according to another embodiment of the disclosure.
Detailed Description
In order to enable those skilled in the art to better understand the technical solutions of the embodiments of the present disclosure, the embodiments of the present disclosure are described in further detail below with reference to the accompanying drawings and detailed description.
The workflow of the core power controller, i.e. the principle of operation of the core power controller automatic control, is illustrated schematically in fig. 1. Specifically, the nuclear power controller inputs a nuclear power set value, deviations are generated from measured values, the nuclear power deviation signal controls a control rod to act through the differential and proportional actions of the nuclear power controller, after the control rod acts, a core power value change is generated in a reactor core of the reactor, a nuclear power measured value is generated through the core power value change, the nuclear power measured value is fed back to the nuclear power controller, the nuclear power deviation signal is generated through comparing the nuclear power measured value with the nuclear power set value, the nuclear power controller is regulated and controlled by utilizing the nuclear power deviation signal, the nuclear power measured value is close to the nuclear power set value as much as possible, and the automatic control of the nuclear power controller is realized according to the deviations between the nuclear power measured value and the nuclear power set value.
As shown in fig. 2, an aspect of an embodiment of the present disclosure provides a simulation method S100 of a high temperature gas cooled reactor nuclear power control system, where the method S100 includes:
s110, performing differential action on the nuclear power controller, and applying negative reactive disturbance with the amplitude range of-15 pcm to-5 pcm to the nuclear power controller.
Specifically, the core power controller is placed in an automatic adjustment state, and is made to perform only differentiation by setting the proportional gain to 0, that is, turning off the proportional action.
After differentiating the nuclear power controller, applying negative reactive disturbance with the amplitude ranging from-15 pcm to-5 pcm to the nuclear power controller.
Preferably, after differentiating the core power controller, a negative reactive disturbance in the amplitude range-10 pcm is introduced by inserting a compensation rod at maximum speed, and then the dynamic response curve of the closed loop is measured.
S120, according to the negative reactivity disturbance, a closed-loop dynamic response curve of each process state variable of the nuclear power control system under the differential action under different differential time constants is obtained.
Specifically, in this embodiment, according to the negative reactive disturbance with the amplitude of-10 pcm, the differential time constant of the core power controller is adjusted, so as to obtain a closed-loop dynamic response curve of each process state variable of the core power control system from the initial state to the steady state under different differential time constants, so as to obtain the closed-loop dynamic response curve of the core power control system under the differential action.
In this embodiment, the process state variables include control rod actuator drive signals, control rod positions, nuclear power, reactor outlet helium temperature, evaporator outlet vapor temperature, and output thermal power.
It should be noted that the differential time constant of the core power controller is adjusted to be in the range of 0.5 to 5. Specifically, in the present embodiment, the differential time constants D are selected to be 0.5, 2.5, and 5, respectively.
That is, according to the negative reactive disturbance with the amplitude of-10 pcm, the differential time constant of the nuclear power controller is adjusted to obtain a closed-loop dynamic response curve of the process state variables of the control rod driving mechanism driving signal, each control rod position, the nuclear power, the reactor outlet hot helium temperature, the evaporator outlet steam temperature and the output hot power in the nuclear power control system from the initial state to the steady state under the differential action under the differential time constants D of 0.5, 2.5 and 5 respectively, so as to obtain the closed-loop dynamic response curve of the nuclear power control system under the differential action.
S130, selecting a target differential time constant according to the closed loop dynamic response curve under the differential action under different differential time constants.
Specifically, in this step, closed-loop dynamic response curves of the process state variables under differential action under different differential time constants are compared and analyzed, and the response curves can be compared and analyzed by using a method of human eye observation or parameter comparison, so that the response curve with the best performance is found according to the comparison and analysis result, and the differential time constant corresponding to the response curve is taken as the target differential time constant.
In the comparison and analysis process, the comparison and analysis may be performed according to a response curve of a single process state variable, or may be performed by combining response curves of a plurality of process state variables.
Illustratively, the target differential time constant is selected based on the closed loop dynamic response curve under differential action at different differential time constants, specifically including:
the target differential time constant is selected from among the different differential time constants according to at least one of an oscillation magnitude, a short settling time, and a deviation magnitude of the closed-loop dynamic response curve under differential action. More specifically, when comparing and analyzing closed loop dynamic response curves under differential action at different differential time constants, a response curve with small oscillations, short settling time, and small deviation is selected. That is, a differential time constant is selected that minimizes both the amount of transient overshoot and settling time and minimizes the deviation. That is, an optimal differential time constant is selected.
In this embodiment, the disturbance is negative reactivity of-10 pcm, the proportional gain is 0, the differential time constants D are d=0.5, d=2.5 and d=5, the control rod driving mechanism driving signal, the nuclear power, the reactor outlet hot helium temperature, the evaporator outlet steam temperature and the output hot power are simulated in sequence, the comprehensive data analysis is appropriate when d=2.5, and the whole curve is the most stable. That is, the target differential time constant is d=2.5.
Through the target differential time constant, the core power can be accurately controlled when the core power controller actually operates, and the frequent disturbance of a unit is avoided when the engineering is actually applied.
S140, respectively performing differential action and proportional action on the nuclear power controller, and applying a negative/positive step disturbance signal with a nuclear power set value in an amplitude range of 0.1% -0.5% to the nuclear power controller, wherein the differential time constant of the nuclear power controller is the target differential time constant.
Specifically, the target differential time constant is used as the differential time constant of the core power controller, and the proportional gain is set to a small value, that is, the core power controller is differentiated and proportioned, respectively. And then, applying a negative/positive step disturbance signal with a nuclear power set value in the amplitude range of 0.1-0.5% to the nuclear power controller, wherein the positive step disturbance signal with the nuclear power set value can cause the rotating speed of the control rod stepping motor to rise, and the negative step disturbance signal with the nuclear power set value can cause the rotating speed of the control rod stepping motor to fall. The response curve of the loop is measured and the proportional gain is gradually increased.
S150, according to the negative/positive step disturbance signals of the core power set value, obtaining closed loop dynamic response curves of all process state variables of the core power control system under differential action and proportional action under different proportional gains.
Specifically, according to a negative/positive step disturbance signal of a nuclear power set value with the amplitude range of 0.1% -0.5%, the proportional gain of the nuclear power controller is adjusted, and a closed-loop dynamic response curve of each process state variable of the nuclear power control system from the initial state to the steady state under different proportional gains is obtained, so that the closed-loop dynamic response curve of the nuclear power control system under the differential action and the proportional action is obtained. Preferably, in this embodiment, a negative/positive step disturbance signal is applied with a core power set point of 0.3% amplitude.
In this embodiment, the process state variables include control rod actuator drive signals, control rod positions, nuclear power, reactor outlet helium temperature, evaporator outlet vapor temperature, and output thermal power.
It should be further noted that the process of adjusting the proportional gain of the core power controller includes: the proportional gain is set to be a smaller value, and the proportional gain is gradually increased so as to accelerate the convergence speed of the measured value to the set value and eliminate deviation.
Wherein the adjustment range of the proportional gain is 0.2-10, in this embodiment, the values of the proportional gain P are set to 0.2, 2, 5 and 10 in order. The adjustment range of the proportional gain is 0.2-10, so that on one hand, the convergence speed of the measured value to the set value can be increased, deviation can be eliminated, and on the other hand, oscillation and unstable closed loop caused by overlarge gain can be avoided.
That is, according to the negative/positive step disturbance signal with amplitude of 0.3% of the nuclear power set value, the proportional gain of the nuclear power controller is adjusted to obtain a closed-loop dynamic response curve of the process state variables of the control rod driving mechanism driving signal, each control rod position, the nuclear power, the reactor outlet hot helium temperature, the evaporator outlet steam temperature and the output hot power in the nuclear power control system from the initial state to the steady state when the proportional gain is 0.2, 2, 5 and 10 respectively, so as to obtain the closed-loop dynamic response curve of the nuclear power control system under the differential action and the proportional action.
S160, selecting a target proportional gain according to the closed loop dynamic response curves under the differential action and the proportional action under different proportional gains.
Specifically, in this step, when comparing and analyzing closed loop dynamic response curves of the core power control system under differential action and proportional action under different proportional gains, the response curves can be compared and analyzed by using a method of human eye observation or parameter comparison, so that the response curve with the best performance is found according to the comparison and analysis result, and the proportional gain corresponding to the response curve is taken as the target proportional gain.
In the comparison and analysis process, the comparison and analysis may be performed according to a response curve of a single process state variable, or may be performed by combining response curves of a plurality of process state variables.
Illustratively, the selecting the target proportional gain according to the closed-loop dynamic response curve under the differential action and the proportional action specifically includes:
the target proportional gain is selected from among the different proportional gains according to at least one of the magnitude of oscillation, the short settling time, and the magnitude of deviation of the closed loop dynamic response curve under differential action and proportional action. More specifically, when comparing and analyzing closed loop dynamic response curves under differential action and proportional action at different proportional gains, a response curve with small oscillations, short settling time, and small deviation is selected. That is, a proportional gain is selected that minimizes both the amount of overshoot and settling time, and minimizes the offset. That is, an optimal proportional gain is selected.
In this embodiment, a negative/positive step disturbance signal with a magnitude of 0.3% is applied to the nuclear power set point, the proportional gains are p=0.2, p=2, p=5 and p=10, the differential time constant is d=2.50, and the control rod driving mechanism driving signal, the nuclear power, the reactor outlet hot helium temperature, the evaporator outlet steam temperature and the output hot power are simulated in sequence, so that comprehensive data analysis is performed, the comprehensive data analysis is appropriate when p=2, d=2.5, and the curve is the whole is the most stable.
Through the target proportional gain, the core power can be accurately controlled when the core power controller actually operates, and the frequent disturbance of a unit is avoided when the engineering is actually applied.
In this embodiment, fig. 3 to fig. 7 are simulation graphs of a nuclear power control system of a simulation method of a nuclear power control system of a high temperature gas cooled reactor under differential action, and in fig. 3 to fig. 7, the setting of parameters includes:
taking the 100% rfp power level test as an example, the core power control system closed loop test:
perturbation was a negative reactivity of-10 pcm applied;
the proportional gain of the proportional action is 0, and the differential time constants of the differential action are d=0.5, respectively; d=2.5; d=5;
and sequentially intercepting simulation results of driving signals of all process state variable control rod driving mechanisms of the nuclear power control system, nuclear power, hot helium temperature at the outlet of the reactor, steam temperature at the outlet of the evaporator and output thermal power. Wherein fig. 3-7 are closed loop dynamic response curves of the process state variable from initial to steady state at different differential time constants, respectively.
As shown in FIG. 3, applying a negative reactivity of-10 pcm, the core power measurement will be lower than the core power set point, and as the core power measurement decreases, the control stick lifts up, resulting from the curve, the stronger the differential action, the larger the corresponding control stick action amplitude, the faster the disturbance action time is overcome, but the too strong differential parameter will cause the system to oscillate, and the parameter needs to be analyzed together with reference to the core power curve, considering whether the parameter is suitable or not.
As shown in fig. 4, when negative reactivity of-10 pcm is applied, the measured value of nuclear power will be lower than the set value of nuclear power, as the measured value of nuclear power decreases, the control rod lifts up, the stronger the differentiating action, the larger the corresponding control rod action amplitude, as can be seen from the curve, the stronger the differentiating action, the quicker the measured value of nuclear power responds, the smaller the range deviating from the set value of nuclear power, i.e. the more obvious the effect of inhibiting the decrease of nuclear power, in combination with considering the overshoot of the measured value of nuclear power to the set value of nuclear power, when the differentiating time constant d=2.5, the parameter is more suitable, the duration of the decrease of the measured value of nuclear power after disturbance is shorter, and the callback into a stable state is faster.
As shown in fig. 5, when negative reactivity of-10 pcm is applied, the measured nuclear power will be lower than the set nuclear power value, and as the measured nuclear power value decreases, the control rod rises, the stronger the differentiation, the slower the temperature of the hot helium decreases, and when the differentiation time constant d=2.5, the whole curve is the most stable, and the steady working condition is the fastest, and the stabilized temperature of the hot helium decreases slightly as the trend of the nuclear power.
As shown in fig. 6, when negative reactivity of-10 pcm is applied, the measured nuclear power value is lower than the set nuclear power value, and as the measured nuclear power value is reduced, the control rod rises, the stronger the differentiating action is, the slower the vapor temperature at the outlet of the evaporator is reduced, the whole curve is the most stable when the differentiating time constant d=2.5, the fastest stable working condition is entered, and the vapor temperature at the outlet of the evaporator after the stabilization is reduced by a small extent as the trend of the nuclear power is the same.
As shown in fig. 7, when negative reactivity of-10 pcm is applied, the measured value of the nuclear power is lower than the set value of the nuclear power, and as the measured value of the nuclear power is reduced, the control rod rises, the stronger the differentiating action is, the slower the output thermal power is reduced, the whole curve is the most stable when the differentiating time constant d=2.5, the fastest stable working condition is entered, and the output thermal power after being stabilized is reduced by a small extent as the trend of the nuclear power is the same.
In summary, the perturbation is a negative reactivity of-10 pcm applied; the proportional gain of the proportional action is 0, the differential time constants of the differential action are D=0.5, D=2.5 and D=5, the driving signal of the control rod transmission mechanism, the nuclear power, the hot helium temperature at the outlet of the reactor, the steam temperature at the outlet of the evaporator and the output thermal power are simulated in sequence, the comprehensive data analysis is carried out, the differential time constant D=2.5 is proper, and the whole curve is the most stable.
It should be noted that, the simulation verification in the present embodiment is only illustrative, that is, the selection and analysis of experimental parameters are both illustrative, and the simulation verification is not limited to the above method.
In this embodiment, fig. 8 to 12 are simulation graphs of a nuclear power control system of a simulation method of a nuclear power control system of a high temperature gas cooled reactor under proportional action and differential action, and in fig. 8 to 12, the setting of parameters includes:
taking the 100% rfp power level test as an example, the core power control system closed loop test:
the disturbance is a negative/positive step disturbance signal applied with a core power set point of 0.3%;
proportional gain for proportional action is p=0.2, p=2, p=5 and p=10, respectively, and differential time constant for differential action is d=2.5;
and intercepting driving signals of the control rod transmission mechanism, nuclear power, hot helium temperature at the outlet of the reactor, steam temperature at the outlet of the evaporator and outputting a thermal power simulation result in sequence. Fig. 8-12 are closed-loop dynamic response curves of the process state variable from initial to steady state at different proportional gains, respectively.
As shown in fig. 8, when a step disturbance signal of 0.3% of the core power set point is applied, the core power measured value is lower than the core power set point, and as the core power measured value is reduced, the control rod lifts up, and is derived from the curve, the differential action is fixed, the stronger the proportional action is, the larger the corresponding control rod action amplitude is, the larger the proportional action is, the oscillation of the system is caused, and whether the parameter is suitable or not is considered, and the control rod needs to be analyzed together with reference to the core power curve. Compared with the pure differential state, the control rod acts more reasonably and the stabilizing time is shorter.
As shown in FIG. 9, a 0.3% nuclear power setpoint step disturbance signal is applied, the nuclear power measurement will be below the nuclear power setpoint, and the control rod is lifted as the nuclear power measurement decreases. From the curve, the differentiation effect is fixed, the stronger the proportional effect, the quicker the response of the core power measurement value is, the smaller the range of the deviation from the core power set point is, and when the proportional gain p=2, the oscillation is relatively minimum, the callback time is proper, and the stabilization time is shorter in combination with considering the overshoot of the core power measurement value to the core power set point. When the proportional gain p=0.2, the adjustment amplitude of the core power measurement value after the disturbance is applied is too small to meet the adjustment requirement. When the proportional gain P is too large, the system oscillates greatly, which is not beneficial to stability and safety.
As shown in fig. 10, a step disturbance signal of 0.3% of the nuclear power set point is applied, the nuclear power measured value is lower than the nuclear power set point, and as the nuclear power measured value is reduced, the temperature of the hot helium is reduced, the proportion is too small, and the temperature of the hot helium is stable for a longer time; the proportion action is proper, the time for the temperature of the hot helium to enter the stabilization is short, and the parameter is stable as a whole after the stabilization.
As shown in fig. 11, a step disturbance signal with a nuclear power set value of 0.3% is applied, the nuclear power measured value is lower than the nuclear power set value, and as the nuclear power measured value is reduced, the outlet steam temperature of the evaporator is reduced, the proportion is too small, and the steam temperature is stable for a longer time; the proportion action is proper, the time for the steam temperature to enter stability is short, and the parameters are stable as a whole after stability.
As shown in fig. 12, when a step disturbance signal of 0.3% of the core power set value is applied, the core power measured value is lower than the core power set value, and as the core power measured value is reduced, the output thermal power is reduced, the proportion is too small, and the output thermal power is stable for a longer time; the proportion action is proper, the time for the output thermal power to enter stability is short, and the parameter is stable as a whole after stability.
To sum up, the perturbation is to apply a nuclear power set point step perturbation signal of 0.3%; the proportional gains of the proportional action are p=0.2, respectively; p=2; d=5; d=10, the differential time constant of the differential action is d=2.5; the driving signals of the control rod transmission mechanism, the nuclear power, the reactor outlet hot helium temperature, the evaporator outlet steam temperature and the output hot power are simulated in sequence, the comprehensive data analysis proportion gain P=2, the differential time constant D=2.5 is proper, and the whole curve is the most stable. Under the disturbance, compared with the differential action, the response time is faster under the proportional action and the differential action, and the action amplitude of the control rod is smaller and more accurate. That is, the target differential time constant is 2.5, and the target proportional gain is 2, so that the nuclear power control system can be better controlled, and the effective operation of the high-temperature gas-cooled reactor can be more accurately controlled.
It should be noted that, the simulation verification in the present embodiment is only illustrative, that is, the selection and analysis of experimental parameters are both illustrative, and the simulation verification is not limited to the above method.
According to the simulation method of the high-temperature gas cooled reactor nuclear power control system, in the debugging process of the nuclear power controller, a target differential time constant and a target proportional gain are obtained according to the closed loop dynamic response curve of each process state variable of the nuclear power control system, and in a multi-input multi-output complex large system such as a high-temperature gas cooled reactor demonstration project, a debugging relationship is established according to the coupling relationship between each control quantity and the regulated quantity through the target differential time constant and the target proportional gain, so that a debugging result can accord with the complex control process of the high-temperature gas cooled reactor, and the accurate control of the nuclear power is realized in actual operation. According to the embodiment of the disclosure, the regulation characteristics of the full-plant power automatic control and regulation system control nuclear power control system can be verified in advance through simulation, so that frequent disturbance for a unit during actual application of engineering is avoided, and the high-temperature gas cooled reactor can be operated safely and reliably according to a debugging result.
As shown in fig. 13, another aspect of the embodiments of the present disclosure provides a simulation apparatus 100 of a high temperature gas cooled reactor nuclear power control system, the apparatus 100 including:
the first setting module 110 is configured to differentiate the core power controller and apply a negative reactive disturbance with an amplitude ranging from-15 pcm to-5 pcm to the core power controller. Specifically, the first setting module 110 applies a negative reactive perturbation to the nuclear power controller with an amplitude in the range of-10 pcm.
The first response curve obtaining module 120 is configured to obtain a closed-loop dynamic response curve of each process state variable of the nuclear power control system under differential action under different differential time constants according to the negative reactive disturbance.
A first selection module 130 is configured to select a target differential time constant according to a closed loop dynamic response curve under differential action at different differential time constants.
And a second setting module 140, configured to perform differential action and proportional action on the core power controller, and apply a negative/positive step disturbance signal with a magnitude range of 0.1% -0.5% to the core power controller, where a differential time constant of the core power controller is the target differential time constant. Specifically, the second setting module 140 applies a negative/positive step disturbance signal to the core power controller with a core power setpoint amplitude of 0.3%.
The second response curve obtaining module 150 is configured to obtain a closed-loop dynamic response curve of each process state variable of the core power control system under the differential action and the proportional action under different proportional gains according to the negative/positive step disturbance signal of the core power setting value.
A second selection module 160 is configured to select the target proportional gain according to a closed loop dynamic response curve under differential action and proportional action described below at different proportional gains.
According to the simulation device of the high-temperature gas cooled reactor nuclear power control system, in the debugging process of the nuclear power controller, a target differential time constant and a target proportional gain are obtained according to the closed loop dynamic response curve of each process state variable of the nuclear power control system, and in a multi-input multi-output complex large system such as a high-temperature gas cooled reactor demonstration project, a debugging relationship is established according to the coupling relationship between each control quantity and the regulated quantity through the target differential time constant and the target proportional gain, so that a debugging result can accord with the complex control process of the high-temperature gas cooled reactor, and the accurate control of the nuclear power is realized in actual operation. According to the embodiment of the disclosure, the regulation characteristics of the full-plant power automatic control and regulation system control nuclear power control system can be verified in advance through simulation, so that frequent disturbance for a unit during actual application of engineering is avoided, and the high-temperature gas cooled reactor can be operated safely and reliably according to a debugging result.
It is to be understood that the above implementations are merely exemplary implementations employed to illustrate the principles of the disclosed embodiments, which are not limited thereto. Various modifications and improvements may be made by those skilled in the art without departing from the spirit and substance of the embodiments of the disclosure, and these modifications and improvements are also considered to be within the scope of the embodiments of the disclosure.
Claims (10)
1. The simulation method of the high-temperature gas cooled reactor nuclear power control system is characterized by comprising the following steps of:
performing differential action on a nuclear power controller, and applying negative reactive disturbance with the amplitude range of-15 pcm to-5 pcm to the nuclear power controller;
according to the negative reactive disturbance, a closed-loop dynamic response curve of each process state variable of the nuclear power control system under the differential action under different differential time constants is obtained;
selecting a target differential time constant according to the closed loop dynamic response curve under the differential action under different differential time constants;
performing differential action and proportional action on the core power controller respectively, and applying a negative/positive step disturbance signal with a core power set value in an amplitude range of 0.1% -0.5% to the core power controller, wherein the differential time constant of the core power controller is the target differential time constant;
obtaining closed loop dynamic response curves of all process state variables of the nuclear power control system under differential action and proportional action under different proportional gains according to the negative/positive step disturbance signals of the nuclear power set value;
the target proportional gain is selected based on the closed loop dynamic response curves under differential action and proportional action described under different proportional gains.
2. The method of claim 1, wherein said deriving a closed-loop dynamic response curve for each process state variable of said nuclear power control system under differential action at different differential time constants from said negative reactive perturbation comprises:
and according to the negative reactive disturbance, adjusting a differential time constant of the nuclear power controller to obtain a closed-loop dynamic response curve of each process state variable of the nuclear power control system from the initial state to the steady state under different differential time constants so as to obtain the closed-loop dynamic response curve of the nuclear power control system under the differential action.
3. The method of claim 2, wherein said adjusting a differential time constant of said core power controller comprises:
the differential time constant of the core power controller is adjusted to be in the range of 0.5-5.
4. A method according to any one of claims 1 to 3, wherein said selecting a target differential time constant based on said closed loop dynamic response curve under differential action at different differential time constants comprises:
the target differential time constant is selected from among different differential time constants according to at least one of the oscillation magnitude, the short settling time and the deviation magnitude of the closed-loop dynamic response curve under differential action.
5. A method according to any one of claims 1 to 3, wherein said applying a negative reactive perturbation to the nuclear power controller having a magnitude in the range-15 to-5 pcm comprises:
inserting the compensation rod at maximum speed introduces a negative reactive disturbance with an amplitude ranging from-15 to-5 pcm.
6. A method according to any one of claims 1 to 3, wherein said obtaining a closed loop dynamic response curve of each process state variable of said core power control system under differential action and proportional action at different proportional gains from a negative/positive step disturbance signal of said core power setpoint comprises:
and adjusting the proportional gain of the nuclear power controller according to the negative/positive step disturbance signal of the nuclear power set value to obtain a closed-loop dynamic response curve from the initial state to the steady state of each process state variable of the nuclear power control system under different proportional gains so as to obtain the closed-loop dynamic response curve of the nuclear power control system under the differential action and the proportional action.
7. The method of claim 6, wherein said adjusting the proportional gain of the core power controller comprises:
setting the proportional gain to a smaller value and gradually increasing the proportional gain; wherein the adjustment range of the proportional gain is 0.2-10.
8. A method according to any one of claims 1 to 3, wherein said selecting a target proportional gain based on said closed loop dynamic response curve under differential action and proportional action comprises:
the target proportional gain is selected from among the different proportional gains according to at least one of oscillation magnitude, short settling time, and deviation magnitude of the closed-loop dynamic response curve under differential action and proportional action.
9. A method according to any one of claims 1 to 3, wherein the process state variables comprise at least one of control rod drive signals, control rod positions, nuclear power, reactor outlet hot helium temperature, evaporator outlet steam temperature, and output thermal power.
10. A simulation device of a high temperature gas cooled reactor nuclear power control system, the device comprising:
the first setting module is used for differentiating the nuclear power controller and applying negative reactive disturbance with the amplitude range of-15 pcm to-5 pcm to the nuclear power controller;
the first response curve acquisition module is used for acquiring a closed-loop dynamic response curve of each process state variable of the nuclear power control system under the differential action under different differential time constants according to the negative reactive disturbance;
the first selection module is used for selecting a target differential time constant according to the closed-loop dynamic response curve under the differential action under different differential time constants;
the second setting module is used for respectively performing differential action and proportional action on the nuclear power controller and applying a negative/positive step disturbance signal with a nuclear power set value in an amplitude range of 0.1% -0.5% to the nuclear power controller, wherein the differential time constant of the nuclear power controller is the target differential time constant;
the second response curve acquisition module is used for acquiring a closed-loop dynamic response curve of each process state variable of the nuclear power control system under the differential action and the proportional action under different proportional gains according to the negative/positive step disturbance signal of the nuclear power set value;
and the second selection module is used for selecting a target proportional gain according to the closed loop dynamic response curves under the differential action and the proportional action under different proportional gains.
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