CN103268728A - Method for constructing power system dynamic simulation pressurized water reactor control system model - Google Patents

Abstract

The invention provides a method for constructing a power system dynamic simulation pressurized water reactor control system model. The method for constructing the power system dynamic simulation pressurized water reactor control system model comprises the steps that appropriate simplification and functional integration are conducted on an actual reactor control system, the reactor control system is decomposed into two sub systems according to functions, namely, a power control system and a temperature control system. The power control system and the temperature control system are used for stimulating that a nuclear power unit controls power to rise or reduce under a normal operating condition, simulating the nuclear power unit to adjust temperature and the power and maintaining stable operation under the situation that the power, voltage and frequency electric parameters disturb, and achieving electromechanical transient and medium and long term dynamic simulation of a large-scale power system including the pressurized water reactor nuclear power unit. By means of the method for constructing the power system dynamic simulation pressurized water reactor control system model, the problems that no accurate reactor control system model exists in an existing simulated program, and therefore dynamic characteristics of the nuclear power unit can not be actually reflected are solved, and a powerful tool for researching problems of the transition process inside the nuclear power unit, the mutual effect between a large-scale power grid and a high-capacity nuclear power unit, source network collaboration and the like is provided.

Description

A kind of Electrical Power System Dynamic emulation pressurized water reactor control system model building method

Technical field

The present invention relates to a kind of field of power, be specifically related in a kind of Electrical Power System Dynamic emulation two generation Fortschrittlicher Druckwasser Reaktor nuclear power generating sets reactor control system model building method.

Background technology

At present, nuclear power is in Large scale construction, accelerated development period.Two generation modified million kilowatt compressed water reactor nuclear power become fortune nuclear power generating sets main body.Because the nuclear power generating sets single-machine capacity is big, safety requirements is high, nuclear power insert after the electric system will and system between produce significant impact, how to guarantee that it is an extremely important problem that nuclear power generating sets and electric system all can move with security and stability.

Power system digital simulation is the basis of ultra-large power system safety and stability operation.In order to study electric system and nuclear power generating sets to ability to bear and the dynamic perfromance mechanism thereof of fault disturbance; the coordination control technology of the control protection of research nuclear power generating sets and power system stability; must consider the singularity of nuclear power generating sets, set up accurately, be applicable to the nuclear power generating sets mathematical model of electric system electromechanical transient and medium-term and long-term dynamic simulation.

The difference of the maximum of compressed water reactor nuclear power unit and conventional unit is reactor, and to the control of reactor and propulsion system output power thereof, is the core of whole nuclear power control system.Though presurized water reactor has good self-stability and from tonality, can not satisfy the requirement to its maneuverability and operational factor definite value, it is very necessary therefore being equipped with corresponding reactor control control system.Position or the boron concentration in reactor core cooling medium of reactor control system by changing control rod changes or keeps reactor capability, and its working condition directly affects the safe operation of total system and the benefit of bringing into play.Therefore reactor control system research had very important practical sense.

But actual compressed water reactor nuclear power unit reactor control system and measurement system, protection system and other control and regulating system interact; in large scale, logic is complicated, degree of accuracy is high, it is bigger to set up corresponding model difficulty in the large-scale electrical power system dynamic simulation program.At present, main flow electric system simulation program such as PSASP, BPA etc. all do not consider the nuclear power generating sets model.Some scholars and expert have successively carried out the nuclear power Modeling Research that is applicable to Electrical Power System Dynamic emulation.But generally speaking, also there are some defectives in the reactor control system of these models, or model is too simple, only describes with transport function, or model has been carried out linearization, rather than derives from basic physical significance.Thereby the degree true to nature of model is restricted, and can not accurately reflect the true dynamic perfromance of actual nuclear power generating sets, still do not possess the condition of applying in the emulation of large scale electric network Electrical Power System Dynamic.

Summary of the invention

The objective of the invention is to overcome above-mentioned defective of the prior art, a kind of construction method of Electrical Power System Dynamic emulation pressurized water reactor control system model is provided, realization comprises large-scale electrical power system electromechanical transient and the medium-term and long-term dynamic simulation of pressurized water reactor nuclear power generating sets, truly reflects the nuclear power generating sets dynamic perfromance.For between the transient process of research nuclear power generating sets inside, large scale electric network and the big capacity nuclear power generating sets influence each other and the source is netted problem such as coordination strong instrument is provided.

Purpose of the present invention adopts following technical proposals to be achieved:

A kind of Electrical Power System Dynamic emulation pressurized water reactor control system model building method, its improvements are, be power control system and two subsystems of temperature control system with the pressurized water reactor control system by Function Decomposition, be used under the normal operating condition of simulation nuclear power generating sets being promoted or reducing the control of power, and under emergent power, voltage and frequency electric parameters disturbance situation, temperature, power are regulated, realized comprising large-scale electrical power system electromechanical transient and the medium-term and long-term dynamic simulation of pressurized water reactor nuclear power generating sets; Concrete steps are as follows:

Step 1: T=0 computing time is set, the beginning simulation calculation;

Step 2: with parameter initialization; Parameter comprises trend basic data, grid equivalent parameters, conventional dynamic element and nuclear power generating sets pile neutron dynamics, thermal-hydraulic parameter.

Step 3: carry out the calculating of power control system model;

Step 4: carry out the calculating of temperature control system model;

Step 5: differentiate the concluding time that whether has arrived setting, if the time to then changing step 6 over to, is carried out next one circulation otherwise return step 3;

Step 6: finish the calculating of power control system model and the calculating of temperature control system model.

Wherein, the computing method of power control system model comprise the steps:

Step (1): calculate this step-length analog quantity and quantity of state according to the iterative algorithm of setting;

Step (2): the reactor power control system model obtains mechanical output, electromagnetic power, steam turbine power, steam turbine load reference value, primary frequency modulation signal, busbar voltage and frequency signal from corresponding nuclear power generating sets model, carry out model solution;

Step (3): obtain steam turbine load power setting valve;

Step (4): calculate the final power setting valve of nuclear power generating sets according to steam turbine mechanical output and generator electromagnetic power;

Step (5): the final power setting valve of nuclear power generating sets in the steam turbine load power setting valve in the comparison step (3) and the step (4), get its large one and be set value of the power;

Step (6): calculate link through the dead band by the set value of the power in the step (5) and obtain adjustment dead band, power control rod rod position;

Step (7): set link by the set value of the power in the step (5) through the rod position, and through inertial element, obtain power control rod reference bar place value;

Step (8): by excellent biased difference signal between power control rod reference bar place value and the actual measurement rod place value, and adjustment dead band, power control rod position, calculate the excellent fast signal that link obtains power control rod through rod speed;

Step (9): to power control rod speed integration, obtain the power control rod position;

Step (10): finish this step-length power control rod model and calculate, change temperature control rod model over to and calculate.

Wherein, described power control system model adopts the mode of open loop that power control rod is adjusted to the desired position rapidly, makes the output power of reactor be adapted to required load.

Wherein, in the step (3), steam turbine primary frequency modulation signal is handled through the primary frequency modulation dead band, produces the frequency compensation signal, adds the steam turbine load value and power reference, obtains steam turbine load power setting valve.

Wherein, step (6)-step (9) obtains in the process of power control rod position, adopts the hysteresis ring mode that variable skip distance is set, and wherein skip distance is determined by the nuclear power generating sets real power.

Wherein, the computing method of temperature control system model comprise the steps:

Step (11): a circuit cools agent medial temperature is passed through inertial element and lead-lag link successively, obtain for a loop medial temperature after the correction of calculating;

Step (12): calculate the final power setting valve of nuclear power generating sets according to steam turbine mechanical output and generator electromagnetic power;

Step (13): more final power setting valve and steam turbine impulse type stage pressure, get its big value, and through first order inertial loop, obtain the set value of the power of actuation temperature control rod;

Step (14): set value of the power calculates link and inertial element through desired temperature, obtains the temperature reference value of temperature control rod;

Step (15): set value of the power obtains the variable temperatures gain by the variable gain link, is used for making the open-loop gain of power mismatch passage basic identical under different operating modes, thereby obtains comparatively reasonably dynamic individual features;

Step (16): reality is examined the poor of power and set value of the power, through a WASHOUT link, obtain the non-linear gain of temperature;

Step (17): being multiplied each other by the non-linear gain of the variable gain of step (15) and step (16) obtains revising the back gain, by gaining after a loop medial temperature and the above-mentioned correction after the correction that the temperature reference value in the step (14) is deducted respectively in the step (11), obtain the temperature deviation for the actuation temperature control rod again;

Step (18): temperature deviation obtains the adjustment rod speed of temperature control rod through hysteresis ring;

Step (19): temperature control rod speed integration is obtained temperature control rod position;

Step (20): reactive calculating introduced in power control rod position, temperature control rod position, and export result of calculation to nuclear power generating sets thermal-hydraulic system model.

Wherein, described temperature control system model adopts the mode of closed loop to regulate, and progressively coolant temperature is adjusted to meet the given medial temperature set-point of cooling medium medial temperature program.

Wherein, in the step (11), pressurized water reactor control system model is with the input as coolant temperature of the mean value of heat pipe section temperature and cold leg temperature in the Electrical Power System Dynamic emulation.

Compared with prior art, the beneficial effect that reaches of the present invention is:

The invention provides pressurized water reactor control system model building method in a kind of Electrical Power System Dynamic emulation, can realize in the practical power systems two generation the Fortschrittlicher Druckwasser Reaktor nuclear power generating sets control system accurately simulate, can carry out interface with nuclear power generating sets one loop thermal-hydraulic system model, secondary circuit electrical system, constitute the complete model of nuclear power generating sets, realize containing the large-scale electrical power system dynamic simulation of compressed water reactor nuclear power unit.

The present invention can realize the accurate simulation to pressurized water reactor control system model in the Electrical Power System Dynamic emulation in the large-scale electrical power system; overcome in the past simulation software and can not accurately simulate the shortcoming of nuclear power generating sets control system dynamic behaviour; be the transient process of research nuclear power station inside, the coordination control technology that the research nuclear power generating sets are controlled protection and power system stability, and the rule that influences each other between large scale electric network and the big capacity nuclear power generating sets provides strong instrument.

The temperature of pressurized water reactor control system model control has been carried out the self-adaptation adjustment to the mismatch degree of reactor real power and power given value in the Electrical Power System Dynamic emulation of the present invention: when the mismatch power variation rate hour, regulating action corresponding a little less than, when the mismatch power variation rate was big, regulating action was stronger; When load hour, regulating action is stronger, when load is big, regulating action a little less than.Thereby embodied the regulating action of actual temperature control system when low-power and power mismatch rate of change are big preferably, made the reactor characteristics of even running more.

The present invention in the Electrical Power System Dynamic simulated program, set up with real system in the consistent model of two generation modified million kilowatt compressed water reactor nuclear power unit reactor control system dynamic perfromances used, can carry out effective emulation to the full dynamic process of nuclear power generating sets, whole continuous dynamic process after accurately the simulation nuclear power generating sets are disturbed, solved and lacked nuclear power generating sets reactor control system model accurately in the existing simulated program, can't reflect the shortcoming of nuclear power generating sets dynamic behaviour truly.

Description of drawings

Fig. 1 is power control system model synoptic diagram provided by the invention;

Fig. 2 is temperature control system model synoptic diagram provided by the invention

Fig. 3 is provided by the invention according to set value of the power accounting temperature setting value;

Fig. 4 is the process flow diagram of pressurized water reactor control system model building method provided by the invention.

Embodiment

Below in conjunction with accompanying drawing the specific embodiment of the present invention is described in further detail.

Actual compressed water reactor nuclear power unit reactor control system and measurement system, protection system and other control, regulating system interact, and be in large scale, logic is complicated, degree of accuracy is high.Therefore, it is bigger to set up corresponding model difficulty in the large-scale electrical power system dynamic simulation program.For the nuclear power generating sets control system universal model that obtains to analyze for power system stability, present embodiment adopts OO idea about modeling, to two generation the Fortschrittlicher Druckwasser Reaktor control system decompose modeling, and carrying out suitable simplification and function integration, the reactor control system model that finally obtains is made of power control system model and temperature control system model.Described model building method is mainly paid close attention to the line voltage frequency disturbance to the influence of control system, ignores the influence that the fault of equipment own is brought, and does not consider the shutdown control system.

The concrete enforcement of scheme provided by the invention is as follows:

1, power control system constructing plan

Fig. 1 has provided power control system model synoptic diagram.The power control of reactor control system model calculates power control rod according to set value of the power and adjusts dead band and power control rod reference bar place value, and by excellent biased difference signal between power control rod reference bar position and the actual measurement rod position, and above-mentioned adjustment dead band, calculate the excellent fast signal that link obtains power control rod through rod speed, at last power control rod speed integration is obtained the power control rod position.Said method adopts the hysteresis ring mode that variable skip distance is set, and avoids the frequent adjustment of power control rod, and wherein skip distance is determined by the nuclear power generating sets real power.

2, final power setting valve calculates

Operate power when final power setting valve is used as steam-dump system and drops into, or the power when when station service load and under underload, moving.Before extra high voltage circuit breaker or steam turbine dropout, when steam turbine was loaded more than or equal to 30% rated power, final power setting valve was 30% rated power; Before extra high voltage circuit breaker or steam turbine dropout, steam turbine was loaded less than 30% o'clock, and final power setting valve is current power.

3, set value of the power calculates

When steam turbine not during output power, set value of the power is final power setting valve, and heap power will maintain this final power setting valve; And under nominal situation, power rod driving power will be taken as steam turbine power reference value frequency compensation signal, and signal driving power rod action thus.

4, calculate in the dead band of power control rod

The skip distance of power control rod is calculated as follows according to nuclear power generating sets real power curve, wherein, and P ₁Be set value of the power, S ₁Be skip distance, a ₁₀₁, b ₁₀₁, k ₁₀₁Design parameter for input:

${\mathrm{<figure-callout\; id="1"\; label="S"\; filenames="HDA00003120032700012.png"\; state="\{\{state\}\}">S</figure-callout>}}_1=\left\{\begin{array}{cc}{\mathrm{<figure-callout\; id="101"\; label="b"\; filenames="HDA00003120032700021.png"\; state="\{\{state\}\}">b</figure-callout>}}_{101}& 0\&le;{\mathrm{<figure-callout\; id="1"\; label="P"\; filenames="HDA00003120032700012.png"\; state="\{\{state\}\}">P</figure-callout>}}_1<a_{101}\\ {\mathrm{<figure-callout\; id="101"\; label="b"\; filenames="HDA00003120032700021.png"\; state="\{\{state\}\}">b</figure-callout>}}_{101}+{{\mathrm{<figure-callout\; id="101"\; label="K"\; filenames="HDA00003120032700021.png"\; state="\{\{state\}\}">K</figure-callout>}}_{101}}^{*}(P_1-a_{101})& a_{101}\&le;{\mathrm{<figure-callout\; id="1"\; label="P"\; filenames="HDA00003120032700012.png"\; state="\{\{state\}\}">P</figure-callout>}}_1\end{array}\right.;$

5, power control rod position setting value is calculated

Power control rod position setting value can be calculated as follows, wherein, and P ₁Be set value of the power, S ₂Be power control rod position setting value, a ₂₀₁, b ₂₀₁, k ₂₀₁Deng the design parameter that is input:

$S_2=\left\{\begin{array}{cc}{b}_{201}+{k_{201}}^{*}{\mathrm{<figure-callout\; id="1"\; label="P"\; filenames="HDA00003120032700012.png"\; state="\{\{state\}\}">P</figure-callout>}}_1& 0\&le;{\mathrm{<figure-callout\; id="1"\; label="P"\; filenames="HDA00003120032700012.png"\; state="\{\{state\}\}">P</figure-callout>}}_1<a_{201}\\ b_{202}+{k_{202}}^{*}(P_1-a_{201})& a_{201}\&le;{\mathrm{<figure-callout\; id="1"\; label="P"\; filenames="HDA00003120032700012.png"\; state="\{\{state\}\}">P</figure-callout>}}_1<a_{202}\\ b_{203}+{k_{203}}^{*}(P_1-a_{202})& a_{202}\&le;{\mathrm{<figure-callout\; id="1"\; label="P"\; filenames="HDA00003120032700012.png"\; state="\{\{state\}\}">P</figure-callout>}}_1<a_{203}\\ b_{204}{{+k}_{204}}^{*}(P_1-a_{203})& a_{203}\&le;{\mathrm{<figure-callout\; id="1"\; label="P"\; filenames="HDA00003120032700012.png"\; state="\{\{state\}\}">P</figure-callout>}}_1<a_{204}\\ b_{205}+{k_{205}}^{*}(P_1-a_{204})& a_{204}\&le;{\mathrm{<figure-callout\; id="1"\; label="P"\; filenames="HDA00003120032700012.png"\; state="\{\{state\}\}">P</figure-callout>}}_1<a_{205}\\ b_{206}+{k_{206}}^{*}(P_1-a_{205})& a_{205}\&le;{\mathrm{<figure-callout\; id="1"\; label="P"\; filenames="HDA00003120032700012.png"\; state="\{\{state\}\}">P</figure-callout>}}_1<a_{206}\\ b_{207}+{k_{207}}^{*}(P_1-a_{206})& a_{206}\&le;{\mathrm{<figure-callout\; id="1"\; label="P"\; filenames="HDA00003120032700012.png"\; state="\{\{state\}\}">P</figure-callout>}}_1<a_{207}\\ b_{208}+{k_{208}}^{*}(P_1-a_{207})& a_{207}\&le;{\mathrm{<figure-callout\; id="1"\; label="P"\; filenames="HDA00003120032700012.png"\; state="\{\{state\}\}">P</figure-callout>}}_1<a_{208}\\ b_{209}+{k_{209}}^{*}(P_1-a_{208})& a_{208}\&le;{\mathrm{<figure-callout\; id="1"\; label="P"\; filenames="HDA00003120032700012.png"\; state="\{\{state\}\}">P</figure-callout>}}_1<a_{209}\\ b_{210}& a_{209}\&le;{\mathrm{<figure-callout\; id="1"\; label="P"\; filenames="HDA00003120032700012.png"\; state="\{\{state\}\}">P</figure-callout>}}_1\end{array}\right.;$

6, calculate power control rod speed and rod position

When load increased, it is big that the calculation rod position becomes, and actual rod position does not change, and then the biased difference signal of current rod constantly is increase trend with respect to last one, and this deviation is during greater than the dead band, produce excellent fast signal (60 the step/min), the beginning rod withdrawal; Reduce trend if the biased difference signal of current rod constantly is with respect to last one, and when this deviation signal during less than dead band and sluggish width poor (sluggish width be 1 go on foot), stop rod withdrawal.The plunger situation similarly, only this moment excellent biased difference signal be negative.The vibration of connecting in order to eliminate control rod drive mechanisms (CRD)-producing when throwing off, model is provided with hysteresis ring.Realize the biased difference of power control rod is converted to the excellent fast signal of power control rod by above-mentioned steps, further power control rod speed has been pressed the following formula integration, can obtain the power control rod position.

S ₃=S ₃₀+∫V _Pdt；

Wherein, S ₃Be the current rod of power control rod position, S ₃₀Be integration step rod position on the power control rod, V _PFor power control rod is adjusted rod speed.

7, temperature control system constructing plan

Fig. 2 has provided temperature control system model synoptic diagram.The temperature control system of reactor control system model is to calculate temperature reference value and compensation power gain by set value of the power, and poor according to temperature reference value and a loop medial temperature and compensation power gain, obtain the temperature deviation for the actuation temperature control rod, this temperature deviation namely obtains the adjustment rod speed of temperature control rod again through hysteresis ring, obtain temperature control rod position by the fast integration of rod at last.Described temperature control system has been carried out the self-adaptation adjustment to the mismatch degree of reactor real power and power given value, embodied the regulating action of actual temperature control system when low-power and power mismatch rate of change are big preferably, made the reactor characteristics of even running more.

8, a loop medial temperature is measured

Because an actual return is longer, be difficult to measure actual each position temperature, therefore adopt the method that cold leg medial temperature and heat pipe section medial temperature are averaged as a loop medial temperature of calculating usefulness, this method realizes easily, and unlikelyly brings too big error.Consider the time-delay of measurement links and the comparison of subsequent calculations amount, a circuit cools agent medial temperature need be obtained being actually used in the medial temperature of calculating through an inertial element and lead-lag link.

9, the temperature reference value of temperature control system is calculated

Steam turbine load impulse type stage pressure and final set value of the power are got big value, and through first order inertial loop, obtain the set value of the power of temperature control system.Set value of the power calculates link through desired temperature can get desired temperature, can obtain the temperature reference value of temperature control system again through first order inertial loop.The synoptic diagram of accounting temperature setting value as shown in Figure 3.

10, the gain of the compensation power of temperature control system is calculated

The reactor transfer coefficient in order to compensate this nonlinearities change, so that under different operating modes, makes the open-loop gain of power mismatch passage basic identical with the reactor capability nonlinearities change, thereby obtains relatively more rational dynamic response characteristic.At first be calculated as follows variable gain Coe ₁:

${\mathrm{<figure-callout\; id="1"\; label="Coe"\; filenames="HDA00003120032700012.png"\; state="\{\{state\}\}">Coe</figure-callout>}}_1=\left\{\begin{array}{cc}{b}_{401}& P_2<a_{401}\\ b_{401}-{k_{401}}^{*}(P_2-a_{401})& a_{401}\&le;P_2<a_{402}\\ b_{402}-{k_{402}}^{*}(P_2-a_{402})& a_{402}\&le;P_2<a_{403}\\ b_{403}{-k_{403}}^{*}(P_2-a_{403})& a_{403}\&le;P_2<a_{404}\\ b_{404}-{k_{404}}^{*}(P_2-a_{404})& a_{404}\&le;P_2<a_{405}\\ b_{405}& a_{405}\&le;P_2\end{array}\right.;$

Secondly, the difference of temperature control rod driving power and actual nuclear power through a WASHOUT link, is input to following non-linear gain link, calculates non-linear variable gain Coe ₂

${\mathrm{Coe}}_2=\left\{\begin{array}{cc}{-b}_{501}+{k_{502}}^{*}(P_3+1.0)& P_3<-1.0\\ {b_{501}}^{*}{P}_3& -1.0\&le;P_3<\\ b_{501}+{k_{502}}^{*}(P_3-1.0)& 1.0\&le;P_3\end{array},1.0\right.;$

At last, be compensated power gain Coe=Coe ₁* Coe ₂

Wherein, P ₂Be the set value of the power of temperature control system, a ₄₀₁, b ₄₀₁, k ₄₀₁Deng the design parameter that is input:

11, calculate the rod speed of temperature control rod and rod position

According to the temperature reference value T that calculates gained ₁With an actual loop medial temperature, and consider the compensation power gain, obtain temperature deviation Δ T, and deviation is calculated as follows excellent fast V accordingly _TWherein, a ₆₀₁, b ₆₀₁, k ₆₀₇Deng the design parameter that is input:

$V_T\left\{\begin{array}{cc}{b}_{601}& \mathrm{\&Delta;T}<a_{601}\\ b_{602}+{k_{602}}^{*}(\mathrm{\&Delta;T}+1.73)& a_{601}\&le;\mathrm{\&Delta;T}<a_{602}\\ b_{602}& a_{602}<\mathrm{\&Delta;T}<a_{603}\\ V_T& a_{603}<\mathrm{\&Delta;T}<a_{604}\\ 0.0& a_{604}\&le;\mathrm{\&Delta;T}<a_{605}\\ V_T& a_{605}\&le;\mathrm{\&Delta;T}{<a}_{606}\\ b_{606}& a_{606}\&le;\mathrm{\&Delta;T}<a_{607}\\ b_{607}+{k_{607}}^{*}(\mathrm{\&Delta;T}-a_{607})& a_{607}\&le;\mathrm{\&Delta;T}<a_{608}\\ b_{608}& a_{608}\&le;\mathrm{\&Delta;T}\end{array}\right.;$

At last to the fast V of rod _TIntegration namely obtains rod position S ₄:

S ₄=S ₄₀+∫V _Tdt。

Wherein, S ₄Be the current rod of temperature control rod position, S ₄₀Be integration step rod position on the power control rod, V _TFor the temperature control rod is adjusted rod speed.

Fig. 4 is the general flow chart of pressurized water reactor control system model building method in the Electrical Power System Dynamic emulation of the embodiment of the invention, comprises power control model and temperature control mould, and total step of this method is as follows:

Step 101: T=0 computing time is set, the beginning simulation calculation; The overall setting-up time of present embodiment is confirmed by the slip-stick artist according to the scene;

Step 102: with parameter initialization;

Step 103: calculate this step-length analog quantity and quantity of state according to the iterative algorithm of setting;

Step 104: the reactor power control system model obtains mechanical output, electromagnetic power, steam turbine power, steam turbine load reference value, primary frequency modulation signal, busbar voltage and frequency signal from corresponding nuclear power generating sets model, carry out model solution;

Step 105: obtain steam turbine load power setting valve;

Step 106: calculate the final power setting valve of nuclear power generating sets according to steam turbine mechanical output and generator electromagnetic power;

Step 107: the steam turbine load power setting valve in the comparison step 105 and the final power setting valve of the nuclear power generating sets in the step 106, get its large one and be set value of the power;

Step 108: calculate link through the dead band by the set value of the power in the step 107 and obtain adjustment dead band, power control rod rod position;

Step 109: set link by the set value of the power in the step 107 through the rod position, and through inertial element, obtain power control rod reference bar place value;

Step 110: by excellent biased difference signal between power control rod reference bar place value and the actual measurement rod place value, and adjustment dead band, power control rod position, calculate the excellent fast signal that link obtains power control rod through rod speed;

Step 111: to power control rod speed integration, obtain the power control rod position;

Step 112: finish this step-length power control rod model and calculate, change temperature control rod model over to and calculate;

Step 113: a circuit cools agent medial temperature is passed through inertial element and lead-lag link successively, obtain for a loop medial temperature after the correction of calculating;

Step 114: calculate the final power setting valve of nuclear power generating sets according to steam turbine mechanical output and generator electromagnetic power;

Step 115: more final power setting valve and steam turbine impulse type stage pressure, get its big value, and through first order inertial loop, obtain the set value of the power of actuation temperature control rod;

Step 116: set value of the power calculates link and inertial element through desired temperature, obtains the temperature reference value of temperature control rod;

Step 117: set value of the power obtains the variable temperatures gain by the variable gain link, is used for making the open-loop gain of power mismatch passage basic identical under different operating modes, thereby obtains comparatively reasonably dynamic individual features;

Step 118: reality is examined the poor of power and set value of the power, through a WASHOUT link, obtain the non-linear gain of temperature;

Step 119: being multiplied each other by the non-linear gain of the variable gain of step 117 and step 118 obtains revising the back gain, by gaining after a loop medial temperature and the above-mentioned correction after the correction that the temperature reference value in the step 116 is deducted respectively in the step 113, obtain the temperature deviation for the actuation temperature control rod again;

Step 120: temperature deviation obtains the adjustment rod speed of temperature control rod through hysteresis ring;

Step 121: temperature control rod speed integration is obtained temperature control rod position;

Step 122: reactive calculating introduced in power control rod position, temperature control rod position, and export result of calculation to nuclear power generating sets thermal-hydraulic system model.

Step 123: differentiate the concluding time that whether has arrived setting, if the time to then changing step 124 over to, is carried out next one circulation otherwise return step 103 to step 122;

Step 124: finish the calculating of power control system model and the calculating of temperature control system model.

According to pressurized water reactor control system model building method in the Electrical Power System Dynamic emulation of the present invention, wherein, pressurized water reactor control system model is made of power control system model and temperature control system model, do not consider the shutdown control system, the main line voltage frequency disturbance of paying close attention to is ignored the influence that the fault of equipment own is brought to the influence of control system.The present invention adopts OO idea about modeling, to two generation the Fortschrittlicher Druckwasser Reaktor control system decompose modeling.And carry out interface with nuclear power generating sets one loop thermal-hydraulic, secondary circuit electrical system model, realized containing the large-scale electrical power system closed loop dynamic simulation of pressurized water reactor control system model.The present invention can realize the accurate simulation to pressurized water reactor control system action behavior and control characteristic in the large-scale electrical power system, overcome the shortcoming that simulation software in the past can not reflect pressurized water reactor control system model action behavior, the ex-post analysis of complicated and major accident can be carried out, the large-scale electrical power system dynamic simulation can be satisfied to the requirement of nuclear power generating sets system simulation.

Should be noted that at last: only illustrate that in conjunction with above-described embodiment technical scheme of the present invention is not intended to limit.Those of ordinary skill in the field are to be understood that: those skilled in the art can make amendment or are equal to replacement the specific embodiment of the present invention, but these modifications or change are all among the claim protection domain that application is awaited the reply.

Claims (9)

1. Electrical Power System Dynamic emulation pressurized water reactor control system model building method, it is characterized in that, be power control system and two subsystems of temperature control system with the pressurized water reactor control system by Function Decomposition, be used under the normal operating condition of simulation nuclear power generating sets being promoted or reducing the control of power, and under emergent power, voltage and frequency electric parameters disturbance situation, temperature, power are regulated, realized comprising large-scale electrical power system electromechanical transient and the medium-term and long-term dynamic simulation of pressurized water reactor nuclear power generating sets; Described step is as follows:

Step 1: T=0 computing time is set, the beginning simulation calculation;

Step 2: with parameter initialization;

Step 3: carry out the calculating of power control system model;

Step 4: carry out the calculating of temperature control system model;

Step 5: differentiate the concluding time that whether has arrived setting, if the time to then changing step 6 over to, is carried out next one circulation otherwise return step 3;

Step 6: finish the calculating of power control system model and the calculating of temperature control system model.

2. Electrical Power System Dynamic emulation pressurized water reactor control system model building method as claimed in claim 1 is characterized in that parameter comprises trend basic data, grid equivalent parameters, conventional dynamic element and nuclear power generating sets parameter in the step 2.

3. Electrical Power System Dynamic emulation pressurized water reactor control system model building method as claimed in claim 1 is characterized in that the computing method of power control system model comprise the steps:

Step (1): calculate this step-length analog quantity and quantity of state according to the iterative algorithm of setting;

Step (2): the reactor power control system model obtains mechanical output, electromagnetic power, steam turbine power, steam turbine load reference value, primary frequency modulation signal, busbar voltage and frequency signal from corresponding nuclear power generating sets model, carry out model solution;

Step (3): obtain steam turbine load power setting valve;

Step (4): calculate the final power setting valve of nuclear power generating sets according to steam turbine mechanical output and generator electromagnetic power;

Step (5): the final power setting valve of nuclear power generating sets in the steam turbine load power setting valve in the comparison step (3) and the step (4), get its large one and be set value of the power;

Step (6): calculate link through the dead band by the set value of the power in the step (5) and obtain adjustment dead band, power control rod rod position;

Step (7): set link by the set value of the power in the step (5) through the rod position, and through inertial element, obtain power control rod reference bar place value;

Step (8): by excellent biased difference signal between power control rod reference bar place value and the actual measurement rod place value, and adjustment dead band, power control rod position, calculate the excellent fast signal that link obtains power control rod through rod speed;

Step (9): to power control rod speed integration, obtain the power control rod position;

Step (10): finish this step-length power control rod model and calculate, change temperature control rod model over to and calculate.

4. Electrical Power System Dynamic emulation pressurized water reactor control system model building method as claimed in claim 3, it is characterized in that, described power control system model adopts the mode of open loop that power control rod is adjusted to the desired position rapidly, makes the output power of reactor be adapted to required load.

5. Electrical Power System Dynamic emulation pressurized water reactor control system model building method as claimed in claim 3, it is characterized in that, in the step (3), steam turbine primary frequency modulation signal is handled through the primary frequency modulation dead band, produce the frequency compensation signal, add the steam turbine load value and power reference, obtain steam turbine load power setting valve.

6. Electrical Power System Dynamic emulation pressurized water reactor control system model building method as claimed in claim 3, it is characterized in that, step (6)-step (9) obtains in the process of power control rod position, adopt the hysteresis ring mode that variable skip distance is set, wherein skip distance is determined by the nuclear power generating sets real power.

7. Electrical Power System Dynamic emulation pressurized water reactor control system model building method as claimed in claim 1 is characterized in that the computing method of temperature control system model comprise the steps:

Step (11): a circuit cools agent medial temperature is passed through inertial element and lead-lag link successively, obtain for a loop medial temperature after the correction of calculating;

Step (12): calculate the final power setting valve of nuclear power generating sets according to steam turbine mechanical output and generator electromagnetic power;

Step (13): more final power setting valve and steam turbine impulse type stage pressure, get its big value, and through first order inertial loop, obtain the set value of the power of actuation temperature control rod;

Step (14): set value of the power calculates link and inertial element through desired temperature, obtains the temperature reference value of temperature control rod;

Step (15): set value of the power obtains the variable temperatures gain by the variable gain link, is used for making the open-loop gain of power mismatch passage basic identical under different operating modes, thereby obtains comparatively reasonably dynamic individual features;

Step (16): reality is examined the poor of power and set value of the power, through a WASHOUT link, obtain the non-linear gain of temperature;

Step (17): being multiplied each other by the non-linear gain of the variable gain of step (15) and step (16) obtains revising the back gain, by gaining after a loop medial temperature and the above-mentioned correction after the correction that the temperature reference value in the step (14) is deducted respectively in the step (11), obtain the temperature deviation for the actuation temperature control rod again;

Step (18): temperature deviation obtains the adjustment rod speed of temperature control rod through hysteresis ring;

Step (19): temperature control rod speed integration is obtained temperature control rod position;

Step (20): reactive calculating introduced in power control rod position, temperature control rod position, and export result of calculation to nuclear power generating sets thermal-hydraulic system model.

8. Electrical Power System Dynamic emulation pressurized water reactor control system model building method as claimed in claim 7, it is characterized in that, described temperature control system model adopts the mode of closed loop to regulate, and progressively coolant temperature is adjusted to meet the given medial temperature set-point of cooling medium medial temperature program.

9. Electrical Power System Dynamic emulation pressurized water reactor control system model building method as claimed in claim 7, it is characterized in that, in the step (11), pressurized water reactor control system model is with the input as coolant temperature of the mean value of heat pipe section temperature and cold leg temperature in the Electrical Power System Dynamic emulation.

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