CN103268728B - A kind of Power System Dynamic Simulation pressurized water reactor control system model construction method - Google Patents
A kind of Power System Dynamic Simulation pressurized water reactor control system model construction method Download PDFInfo
- Publication number
- CN103268728B CN103268728B CN201310153757.XA CN201310153757A CN103268728B CN 103268728 B CN103268728 B CN 103268728B CN 201310153757 A CN201310153757 A CN 201310153757A CN 103268728 B CN103268728 B CN 103268728B
- Authority
- CN
- China
- Prior art keywords
- power
- control system
- temperature
- system model
- control rod
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Active
Links
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 title claims abstract description 34
- 238000005094 computer simulation Methods 0.000 title claims abstract description 27
- 238000010276 construction Methods 0.000 title claims abstract description 18
- 238000000034 method Methods 0.000 claims abstract description 16
- 230000010354 integration Effects 0.000 claims abstract description 14
- 230000008569 process Effects 0.000 claims abstract description 10
- 238000004088 simulation Methods 0.000 claims abstract description 10
- 230000001052 transient effect Effects 0.000 claims abstract description 8
- 230000007774 longterm Effects 0.000 claims abstract description 5
- 238000000354 decomposition reaction Methods 0.000 claims abstract description 3
- 238000004364 calculation method Methods 0.000 claims description 14
- 239000002826 coolant Substances 0.000 claims description 11
- 230000001105 regulatory effect Effects 0.000 claims description 10
- 238000012937 correction Methods 0.000 claims description 9
- 238000005259 measurement Methods 0.000 claims description 7
- 238000004422 calculation algorithm Methods 0.000 claims description 3
- 239000003795 chemical substances by application Substances 0.000 claims description 2
- 230000007246 mechanism Effects 0.000 abstract description 4
- 238000006243 chemical reaction Methods 0.000 abstract 1
- 230000008859 change Effects 0.000 description 6
- 239000004927 clay Substances 0.000 description 5
- 238000013461 design Methods 0.000 description 4
- 230000009471 action Effects 0.000 description 3
- 238000011160 research Methods 0.000 description 3
- 238000004458 analytical method Methods 0.000 description 2
- 230000007547 defect Effects 0.000 description 2
- 238000010586 diagram Methods 0.000 description 2
- ZOXJGFHDIHLPTG-UHFFFAOYSA-N Boron Chemical compound [B] ZOXJGFHDIHLPTG-UHFFFAOYSA-N 0.000 description 1
- 230000009286 beneficial effect Effects 0.000 description 1
- 230000008901 benefit Effects 0.000 description 1
- 229910052796 boron Inorganic materials 0.000 description 1
- 238000011161 development Methods 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 238000013178 mathematical model Methods 0.000 description 1
- 230000009467 reduction Effects 0.000 description 1
- 230000004044 response Effects 0.000 description 1
- 238000012546 transfer Methods 0.000 description 1
Landscapes
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The invention provides a kind of Power System Dynamic Simulation pressurized water reactor control system model construction method, wherein, by carrying out suitable simplification and Function Integration Mechanism to real reaction heap control system, be power control system and temperature control system two subsystems by reactor control system by Function Decomposition, nuclear power generating sets to be promoted under accidental conditions for simulating or to fall lower powered control, and at emergent power, under voltage and frequency electrical amount disturbance situation, simulation unit is to temperature, power regulates, maintain stable operation, realize the large-scale electrical power system electromechanical transient and the long term dynamics emulation that comprise pressurized water reactor nuclear power generating sets.The invention solves in existing simulated program and lack reactor control system model accurately, truly cannot reflect the problem of nuclear power generating sets dynamic perfromance.For study nuclear power generating sets inside transient process, between large scale electric network and Large Copacity nuclear power generating sets influence each other and source is netted and the problem such as to be coordinated and provide strong instrument.
Description
Technical field
The present invention relates to a kind of field of power, to be specifically related in a kind of Power System Dynamic Simulation 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 nuclear power generating sets single-machine capacity is large, safety requirements is high, nuclear power access electric system after will and system between produce significant impact, how guaranteeing that nuclear power generating sets and electric system all can run with security and stability is an extremely important problem.
Power system digital simulation is the basis that ultra-large power system safety and stability runs.In order to study electric system and nuclear power generating sets to the ability to bear of fault disturbance and dynamic perfromance mechanism thereof; the Coordinated Control of research nuclear power generating sets Control protection and power system stability; the singularity of nuclear power generating sets must be considered, set up accurately, be applicable to the nuclear power generating sets mathematical model of the dynamo-electric transient state of electric system and long term dynamics emulation.
The maximum difference of compacted clay liners and conventional power unit is reactor, and the control to reactor and propulsion system output power thereof, be the core of whole nuclear power control system.Although presurized water reactor has good self-stability and from tonality, can not meet the requirement to its maneuverability and operational factor definite value, it is very necessary for being therefore equipped with corresponding reactor control control system.Reactor control system is changed by the boron concentration changed in the position of control rod or Core cooling agent or is maintained reactor capability, the safe operation that its working condition directly affects whole system and the benefit played.Therefore to reactor control system research, there is very important realistic meaning.
But actual compacted clay liners reactor control system and measurement system, protection system and other controls and regulating system interacts; in large scale, logic is complicated, degree of accuracy is high, sets up corresponding model difficulty larger in large-scale electrical power system dynamic simulation program.At present, prevailing power system simulated program such as PSASP, BPA etc. all do not consider nuclear power generating sets model.Some scholars and expert have successively carried out the nuclear power Modeling Research being applicable to Power System Dynamic Simulation.But generally speaking, the reactor control system of these models also exists some defects, or model is too simple, only describes by transport function, or has carried out linearization to model, instead of derive from basic physical significance.Thus the degree true to nature of model is restricted, and accurately can not reflect the true dynamic perfromance of actual nuclear power generating sets, still not possess the condition applied in large scale electric network Power System Dynamic Simulation.
Summary of the invention
The object of the invention is to overcome above-mentioned defect of the prior art, a kind of construction method of Power System Dynamic Simulation pressurized water reactor control system model is provided, realize the large-scale electrical power system electromechanical transient and the long term dynamics emulation that comprise pressurized water reactor nuclear power generating sets, true reflection nuclear power generating sets dynamic perfromance.For study nuclear power generating sets inside transient process, between large scale electric network and Large Copacity nuclear power generating sets influence each other and source is netted and the problem such as to be coordinated and provide powerful.
Object of the present invention adopts following technical proposals to be achieved:
A kind of Power System Dynamic Simulation pressurized water reactor control system model construction method, its improvements are, be power control system and temperature control system two subsystems by pressurized water reactor control system by Function Decomposition, nuclear power generating sets to be promoted under accidental conditions for simulating or to fall lower powered control, and under emergent power, voltage and frequency electrical amount disturbance situation, temperature, power are regulated, realizes the large-scale electrical power system electromechanical transient and the long term dynamics emulation that comprise pressurized water reactor nuclear power generating sets; Concrete steps are as follows:
Step 1: arrange T=0 computing time, starts simulation calculation;
Step 2: by 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: the calculating carrying out power control system model;
Step 4: the calculating carrying out temperature control system model;
Step 5: differentiate and whether arrived end time of setting, if the time to; proceed to step 6, otherwise return step 3 and carry out the next one and circulate;
Step 6: terminate 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): 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, carries 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 comparison step (3) and step (4), gets its large one for set value of the power;
Step (6): calculate link by the set value of the power in step (5) through dead band and obtain power control rod rod adjustment dead band, position;
Step (7): set link by the set value of the power in step (5) through excellent 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 actual measurement rod place value, and adjustment dead band, power control rod position, calculate through rod speed the rod speed signal that link obtains power control rod;
Step (9): to power control rod speed integration, obtain power control rod position;
Step (10): terminate this step-length power control rod model and calculate, proceeds to temperature control rod model and calculates.
Wherein, described power control system model adopts the mode of open loop that power control rod is adjusted to desired position rapidly, makes the output power of reactor be adapted to required load.
Wherein, in step (3), steam turbine primary frequency modulation signal, through the process of primary frequency modulation dead band, produces frequency compensation signal, adds steam turbine load value and power reference, obtain steam turbine load power setting valve.
Wherein, step (6)-step (9) obtains in the process of power control rod position, and adopt hysteresis ring mode to arrange varied dead zone width, wherein skip distance is determined by nuclear power generating sets real power.
Wherein, the computing method of temperature control system model comprise the steps:
Step (11): by primary Ioops cooling medium medial temperature successively through inertial element and lead-lag link, obtains primary Ioops medial temperature after the correction for 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, gets its large value, and through first order inertial loop, obtains 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 variable temperatures gain by variable gain link, under different operating modes, makes the open-loop gain of power mismatch passage substantially identical, thus obtains comparatively reasonably dynamic individual features;
Step (16): by the difference of actual core power and set value of the power, through a WASHOUT link, obtain the non-linear gain of temperature;
Step (17): to be multiplied with the non-linear gain of step (16) by the variable gain of step (15) and to obtain revising rear gain, again by gain after primary Ioops medial temperature after the correction temperature reference value in step (14) deducted respectively in step (11) and above-mentioned correction, obtain the temperature deviation for actuation temperature control rod;
Step (18): temperature deviation obtains the adjusting rod speed of temperature control rod through hysteresis ring;
Step (19): temperature control rod speed integration is obtained temperature control rod position;
Step (20): power control rod position, temperature control rod position are introduced reactive calculating, and result of calculation exported to nuclear power generating sets thermal-hydraulic system model.
Wherein, described temperature control system model adopts the mode of closed loop to regulate, and is progressively adjusted to by coolant temperature and meets the given medial temperature set-point of cooling medium medial temperature program.
Wherein, in step (11), in Power System Dynamic Simulation, pressurized water reactor control system model is using the mean value of heat pipe section temperature and cold leg temperature as the input of circuit cools agent medial temperature.
Compared with prior art, the beneficial effect that the present invention reaches is:
The invention provides pressurized water reactor control system model construction method in a kind of Power System Dynamic Simulation, can realize in practical power systems two generation Fortschrittlicher Druckwasser Reaktor nuclear power generating sets control system accurate simulation, interface can be carried out with nuclear power generating sets primary Ioops thermal-hydraulic system model, secondary circuit electrical system, form the complete model of nuclear power generating sets, realize the large-scale electrical power system dynamic simulation containing compacted clay liners.
The present invention can realize the accurate simulation to pressurized water reactor control system model in Power System Dynamic Simulation in large-scale electrical power system; overcoming simulation software in the past can not the shortcoming of accurate simulation nuclear power generating sets control system dynamic behaviour; for studying the transient process of nuclear power station inside, studying the Coordinated Control of nuclear power generating sets Control protection and power system stability, and the Mutual Influence Law between large scale electric network and Large Copacity nuclear power generating sets provides strong instrument.
In Power System Dynamic Simulation of the present invention, the temperature of pressurized water reactor control system model controls to have carried out self-adaptative adjustment to the mismatch of reactor real power and power set-point: when mismatch power variation rate is less, regulating action is corresponding more weak, when mismatch power variation rate is larger, regulating action is stronger; When load is less, regulating action is comparatively strong, and when load is larger, regulating action is more weak.Thus embody preferably actual temperature control system low-power and power mismatch rate of change larger time regulating action, make the feature of reactor even running more.
The present invention sets up and the consistent model of two generation modified million kilowatt compacted clay liners reactor control system dynamic perfromances applied in real system in Power System Dynamic Simulation program, effectively can emulate the full dynamic process of nuclear power generating sets, whole continuous print dynamic process after accurate simulation nuclear power generating sets are disturbed, solve in existing simulated program and lack nuclear power generating sets reactor control system model accurately, the shortcoming of nuclear power generating sets dynamic behaviour cannot be reflected truly.
Accompanying drawing explanation
Fig. 1 is power control system model schematic provided by the invention;
Fig. 2 is temperature control system model schematic 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 construction 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 compacted clay liners reactor control system and measurement system, protection system and other control, regulating system interacts, in large scale, logic is complicated, degree of accuracy is high.Therefore, in large-scale electrical power system dynamic simulation program, corresponding model difficulty is set up larger.In order to obtain the nuclear power generating sets control system universal model for Power System Stability Analysis, the present embodiment adopts Object-Oriented Model thought, to two generation Fortschrittlicher Druckwasser Reaktor control system carry out composition model, and carrying out suitable simplification and Function Integration Mechanism, the reactor control system model finally obtained is by power control system model and temperature control system model-composing.Described model building method mainly pays close attention to the impact of line voltage frequency disturbance on control system, ignores the impact that the fault of equipment own is brought, and does not consider Control system of shut down.
Scheme provided by the invention is specifically implemented as follows:
1, power control system constructing plan
Fig. 1 gives power control system model schematic.The power of reactor control system model controls to calculate power control rod adjustment dead band and power control rod reference bar place value according to set value of the power, and by excellent biased difference signal between power control rod reference bar position and actual measurement rod position, and above-mentioned adjustment dead band, calculate through rod speed the rod speed signal that link obtains power control rod, finally power control rod speed integration is obtained power control rod position.Said method adopts hysteresis ring mode to arrange varied dead zone width, and avoid the frequent adjustment of power control rod, wherein skip distance is determined by nuclear power generating sets real power.
2, final power setting valve calculates
Final power setting valve is used as operate power when steam-dump system drops into, or the power when station service load and when running at low load.Before extra high voltage circuit breaker or steam turbine are threaded off, when steam turbine load is more than or equal to 30% rated power, final power setting valve is 30% rated power; Before extra high voltage circuit breaker or steam turbine are threaded off, when steam turbine load is less than 30%, final power setting valve is current power.
3, set value of the power calculates
When steam turbine not output power time, set value of the power is final power setting valve, heap power will maintain this final power setting valve; And in normal conditions, power rod driving power will be taken as steam turbine power reference value frequency compensation signal, and signal driving power rod action thus.
4, the dead band of power control rod calculates
The skip distance of power control rod is calculated as follows according to nuclear power generating sets real power curve, wherein, and P
1for set value of the power, S
1for skip distance, a
101, b
101, k
101design parameter for input:
5, power control rod position preset value calculation
Power control rod position setting value can be calculated as follows, wherein, and P
1for set value of the power, S
2for power control rod position setting value, a
201, b
201, k
201design parameter etc. being input:
6, power control rod speed and excellent position calculate
When load increases, calculation rod position becomes large, and actual excellent position is change not, then the biased difference signal of current rod was increase trend relative to a upper moment, and when this deviation is greater than dead band, produced excellent fast signal (60 steps/min), starts rod withdrawal; If the biased difference signal of current rod was reduction trend relative to a upper moment, and when this deviation signal is less than dead band and sluggish width poor (sluggish width is 1 step), stop rod withdrawal.Plunger situation is similar, and only now excellent biased difference signal is negative.In order to eliminate the vibration produced when control rod drive mechanisms (CRD) is connected-thrown off, model is provided with hysteresis ring.Achieved the rod speed signal biased for power control rod difference being converted to power control rod by above-mentioned steps, further power control rod speed is pressed following formula integration, power control rod position can be obtained.
S
3＝S
30+∫V
Pdt；
Wherein, S
3for the current excellent position of power control rod, S
30for an integration step rod position in power control rod, V
pfor power control rod adjusting rod speed.
7, temperature control system constructing plan
Fig. 2 gives temperature control system model schematic.The temperature control system of reactor control system model calculates temperature reference value and compensation power gain by set value of the power, and according to the difference of temperature reference value and primary Ioops medial temperature and compensation power gain, obtain the temperature deviation for actuation temperature control rod, namely this temperature deviation obtains the adjusting rod speed of temperature control rod again through hysteresis ring, finally obtain temperature control rod position by the fast integration of rod.The mismatch of described temperature control system to reactor real power and power set-point has carried out self-adaptative adjustment, embody preferably actual temperature control system low-power and power mismatch rate of change larger time regulating action, make the feature of reactor even running more.
8, primary Ioops medial temperature is measured
Because actual primary coolant circuit pipe is longer, be difficult to measure actual each spot temperature, therefore adopt the method that cold leg medial temperature and heat pipe section medial temperature is averaged as the primary Ioops cooling medium medial temperature calculated, this method easily realizes, and unlikelyly brings too large error.Consider the time delay of measurement links and the comparison of subsequent calculations amount, need the medial temperature obtaining primary Ioops cooling medium medial temperature to be actually used in through an inertial element and lead-lag link calculating.
9, the temperature reference value of temperature control system calculates
Steam turbine load impulse type stage pressure and final set value of the power are taken large values, and through first order inertial loop, obtains the set value of the power of temperature control system.Set value of the power calculates link through desired temperature can obtain desired temperature, then can obtain the temperature reference value of temperature control system through first order inertial loop.The schematic diagram of accounting temperature setting value as shown in Figure 3.
10, the compensation power gain of temperature control system calculates
Reactor transfer coefficient, with reactor capability nonlinearities change, in order to compensate this nonlinearities change, so that under different operating modes, makes the open-loop gain of power mismatch passage substantially identical, thus obtains the dynamic response characteristic comparing rationality.First variable gain Coe is calculated as follows
1:
Secondly, by the difference of temperature control rod driving power and actual core power through a WASHOUT link, be input to following non-linear gain link, calculate non-linear variable gain Coe
2
Finally, power gain Coe=Coe is compensated
1* Coe
2.
Wherein, P
2for the set value of the power of temperature control system, a
401, b
401, k
401design parameter etc. being input:
11, the rod speed of temperature control rod and excellent position calculate
According to the temperature reference value T calculating gained
1with actual primary Ioops medial temperature, and consider compensation power gain, obtain temperature deviation Δ T, and deviation is calculated as follows excellent fast V accordingly
t.Wherein, a
601, b
601, k
607design parameter etc. being input:
Finally to the fast V of rod
tnamely integration obtains excellent position S
4:
S
4＝S
40+∫V
Tdt。
Wherein, S
4for the current excellent position of temperature control rod, S
40for an integration step rod position in power control rod, V
tfor temperature control rod adjusting rod speed.
Fig. 4 is the general flow chart of pressurized water reactor control system model construction method in the Power System Dynamic Simulation of the embodiment of the present invention, and comprise Power control model and temperature control mould, total step of the method is as follows:
Step 101: arrange T=0 computing time, starts simulation calculation; The overall setting-up time of the present embodiment is confirmed by slip-stick artist according to scene;
Step 102: by parameter initialization;
Step 103: calculate this step-length analog quantity and quantity of state according to the iterative algorithm of setting;
Step 104: 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, carries 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 comparison step 105 and the final power setting valve of the nuclear power generating sets in step 106, gets its large one for set value of the power;
Step 108: calculate link by the set value of the power in step 107 through dead band and obtain power control rod rod adjustment dead band, position;
Step 109: set link by the set value of the power in step 107 through excellent 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 actual measurement rod place value, and adjustment dead band, power control rod position, calculate through rod speed the rod speed signal that link obtains power control rod;
Step 111: to power control rod speed integration, obtain power control rod position;
Step 112: terminate this step-length power control rod model and calculate, proceeds to temperature control rod model and calculates;
Step 113: by primary Ioops cooling medium medial temperature successively through inertial element and lead-lag link, obtains primary Ioops medial temperature after the correction for 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, gets its large value, and through first order inertial loop, obtains 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 variable temperatures gain by variable gain link, under different operating modes, makes the open-loop gain of power mismatch passage substantially identical, thus obtains comparatively reasonably dynamic individual features;
Step 118: by the difference of actual core power and set value of the power, through a WASHOUT link, obtain the non-linear gain of temperature;
Step 119: to be multiplied with the non-linear gain of step 118 by the variable gain of step 117 and to obtain revising rear gain, again by gain after primary Ioops medial temperature after the correction temperature reference value in step 116 deducted respectively in step 113 and above-mentioned correction, obtain the temperature deviation for actuation temperature control rod;
Step 120: temperature deviation obtains the adjusting rod speed of temperature control rod through hysteresis ring;
Step 121: temperature control rod speed integration is obtained temperature control rod position;
Step 122: power control rod position, temperature control rod position are introduced reactive calculating, and result of calculation exported to nuclear power generating sets thermal-hydraulic system model.
Step 123: differentiate and whether arrived end time of setting, if the time to; proceed to step 124, otherwise return step 103 to step 122 and carry out the next one and circulate;
Step 124: terminate the calculating of power control system model and the calculating of temperature control system model.
According to pressurized water reactor control system model construction method in Power System Dynamic Simulation of the present invention, wherein, pressurized water reactor control system model is by power control system model and temperature control system model-composing, do not consider Control system of shut down, main concern line voltage frequency disturbance, on the impact of control system, ignores the impact that the fault of equipment own is brought.The present invention adopts Object-Oriented Model thought, to two generation Fortschrittlicher Druckwasser Reaktor control system carry out composition model.And carry out interface with nuclear power generating sets primary Ioops thermal-hydraulic, secondary circuit electrical system model, achieve the large-scale electrical power system closed loop dynamic simulation containing 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 large-scale electrical power system, overcome simulation software in the past and can not reflect the shortcoming of pressurized water reactor control system model action behavior, ex-post analysis that is complicated and major accident can be carried out, the requirement that large-scale electrical power system dynamic simulation is simulated nuclear power generating sets system can be met.
Finally should be noted that: only illustrate that technical scheme of the present invention is not intended to limit in conjunction with above-described embodiment.Those of ordinary skill in the field are to be understood that: those skilled in the art can modify to the specific embodiment of the present invention or equivalent replacement, but these amendments or change are all being applied among the claims awaited the reply.
Claims (8)
1. a Power System Dynamic Simulation pressurized water reactor control system model construction method, it is characterized in that, be power control system and temperature control system two subsystems by pressurized water reactor control system by Function Decomposition, nuclear power generating sets to be promoted under accidental conditions for simulating or to fall lower powered control, and under emergent power, voltage and frequency electrical amount disturbance situation, temperature, power are regulated, realizes the large-scale electrical power system electromechanical transient and the long term dynamics emulation that comprise pressurized water reactor nuclear power generating sets;
The computing method step of described Power System Dynamic Simulation pressurized water reactor control system model is as follows:
Step 1: arrange T=0 computing time, starts simulation calculation;
Step 3: the calculating carrying out power control system model;
Step 4: the calculating carrying out temperature control system model;
Step 5: differentiate and whether arrived end time of setting, if the time to; proceed to step 6, otherwise return step 3 and carry out the next one and circulate;
Step 6: terminate the calculating of power control system model and the calculating of temperature control system model;
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): 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, carries 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 comparison step (3) and step (4), gets its large one for set value of the power;
Step (6): calculate link by the set value of the power in step (5) through dead band and obtain power control rod rod adjustment dead band, position;
Step (7): set link by the set value of the power in step (5) through excellent 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 actual measurement rod place value, and adjustment dead band, power control rod position, calculate through rod speed the rod speed signal that link obtains power control rod;
Step (9): to power control rod speed integration, obtain power control rod position;
Step (10): terminate this step-length power control rod model and calculate, proceeds to temperature control rod model and calculates.
2. Power System Dynamic Simulation pressurized water reactor control system model construction method as claimed in claim 1, it is characterized in that, in step 2, parameter comprises trend basic data, grid equivalent parameters, conventional dynamic element and nuclear power generating sets parameter.
3. Power System Dynamic Simulation pressurized water reactor control system model construction method as claimed in claim 1, it is characterized in that, described power control system model adopts the mode of open loop that power control rod is adjusted to desired position rapidly, makes the output power of reactor be adapted to required load.
4. Power System Dynamic Simulation pressurized water reactor control system model construction method as claimed in claim 1, it is characterized in that, in step (3), steam turbine primary frequency modulation signal processes through primary frequency modulation dead band, produce frequency compensation signal, add steam turbine load value and power reference, obtain steam turbine load power setting valve.
5. Power System Dynamic Simulation pressurized water reactor control system model construction method as claimed in claim 1, it is characterized in that, step (6)-step (9) obtains in the process of power control rod position, adopt hysteresis ring mode to arrange varied dead zone width, wherein skip distance is determined by nuclear power generating sets real power.
6. Power System Dynamic Simulation pressurized water reactor control system model construction method as claimed in claim 1, it is characterized in that, the computing method of temperature control system model comprise the steps:
Step (11): by primary Ioops cooling medium medial temperature successively through inertial element and lead-lag link, obtains primary Ioops medial temperature after the correction for 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, gets its large value, and through first order inertial loop, obtains 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 variable temperatures gain by variable gain link, under different operating modes, makes the open-loop gain of power mismatch passage substantially identical, thus obtains comparatively reasonably dynamic individual features;
Step (16): by the difference of actual core power and set value of the power, through a WASHOUT link, obtain the non-linear gain of temperature;
Step (17): to be multiplied with the non-linear gain of step (16) by the variable gain of step (15) and to obtain revising rear gain, again by gain after primary Ioops medial temperature after the correction temperature reference value in step (14) deducted respectively in step (11) and above-mentioned correction, obtain the temperature deviation for actuation temperature control rod;
Step (18): temperature deviation obtains the adjusting rod speed of temperature control rod through hysteresis ring;
Step (19): temperature control rod speed integration is obtained temperature control rod position;
Step (20): power control rod position, temperature control rod position are introduced reactive calculating, and result of calculation exported to nuclear power generating sets thermal-hydraulic system model.
7. Power System Dynamic Simulation pressurized water reactor control system model construction method as claimed in claim 6, it is characterized in that, described temperature control system model adopts the mode of closed loop to regulate, and is progressively adjusted to by coolant temperature and meets the given medial temperature set-point of cooling medium medial temperature program.
8. Power System Dynamic Simulation pressurized water reactor control system model construction method as claimed in claim 6, it is characterized in that, in step (11), in Power System Dynamic Simulation, pressurized water reactor control system model is using the mean value of heat pipe section temperature and cold leg temperature as the input of circuit cools agent medial temperature.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201310153757.XA CN103268728B (en) | 2013-04-27 | 2013-04-27 | A kind of Power System Dynamic Simulation pressurized water reactor control system model construction method |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201310153757.XA CN103268728B (en) | 2013-04-27 | 2013-04-27 | A kind of Power System Dynamic Simulation pressurized water reactor control system model construction method |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN103268728A CN103268728A (en) | 2013-08-28 |
| CN103268728B true CN103268728B (en) | 2016-01-20 |
Family
ID=49012355
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201310153757.XA Active CN103268728B (en) | 2013-04-27 | 2013-04-27 | A kind of Power System Dynamic Simulation pressurized water reactor control system model construction method |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN103268728B (en) |
Families Citing this family (14)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104916337B (en) * | 2014-03-14 | 2017-11-24 | 江苏核电有限公司 | A kind of data processing method of control rod calculus value measurement experiment |
| CN103971298A (en) * | 2014-05-26 | 2014-08-06 | 国家电网公司 | Simulation analysis method for nuclear power and power grid mutual interference |
| CN104570769A (en) * | 2015-01-04 | 2015-04-29 | 国家电网公司 | Actual measurement modeling method of power system electromechanical transient model of nuclear power unit speed regulating system |
| CN106528978B (en) * | 2016-11-02 | 2023-07-21 | 中国电力科学研究院 | Dynamic simulation method and system for speed regulation system of advanced pressurized water reactor nuclear motor unit |
| CN106773666B (en) * | 2016-11-11 | 2020-01-10 | 中国电力科学研究院 | Model parameter obtaining method for pressurized water reactor primary circuit system |
| CN109190145B (en) * | 2018-07-12 | 2023-06-16 | 广西电网有限责任公司电力科学研究院 | Nuclear power unit simulation model comprising power control system |
| CN109543223A (en) * | 2018-10-19 | 2019-03-29 | 广西电网有限责任公司电力科学研究院 | A kind of nuclear power unit Theoretic Analysis method |
| CN109783936B (en) * | 2019-01-15 | 2023-07-18 | 国网宁夏电力有限公司电力科学研究院 | Calculation method for variable-working-condition heat accumulation increment of nuclear island of pressurized water reactor nuclear power station |
| CN110767060B (en) * | 2019-08-15 | 2024-10-25 | 西安交通大学 | Nuclear reactor rod control system experimental device and experimental method thereof |
| CN111679569B (en) * | 2020-06-16 | 2021-09-14 | 中国科学院国家授时中心 | Time interval measuring system and method based on mismatched transmission lines |
| CN111930160B (en) * | 2020-07-15 | 2021-08-13 | 岭东核电有限公司 | Method and device for controlling average temperature of nuclear reactor in nuclear power plant |
| CN114077845B (en) * | 2020-08-12 | 2024-01-30 | 中广核（北京）仿真技术有限公司 | Method and system for measuring power-rod position curve of nuclear power station simulation simulator platform |
| CN112394639B (en) * | 2020-11-20 | 2021-08-24 | 西安热工研究院有限公司 | Nuclear power unit control rod adjusting method and system with incremental adjusting function |
| CN113871037A (en) * | 2021-09-14 | 2021-12-31 | 中广核研究院有限公司 | Reactor operation control method, reactor operation control device, computer equipment and storage medium |
Family Cites Families (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP4901631B2 (en) * | 2007-07-30 | 2012-03-21 | 原子燃料工業株式会社 | Method for measuring Doppler reactivity coefficient |
| KR100982774B1 (en) * | 2008-09-30 | 2010-09-16 | 한국전력기술 주식회사 | Performance validation apparatus and method for control systems of nuclear power plant |
| CN102279901B (en) * | 2011-05-17 | 2013-01-09 | 湖北省电力公司电力科学研究院 | Modeling method specific to third generation pressurized water reactor nuclear power generating unit |
-
2013
- 2013-04-27 CN CN201310153757.XA patent/CN103268728B/en active Active
Also Published As
| Publication number | Publication date |
|---|---|
| CN103268728A (en) | 2013-08-28 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN103268728B (en) | A kind of Power System Dynamic Simulation pressurized water reactor control system model construction method | |
| CN104503228B (en) | Primary frequency modulation stability domain determination method of water turbine speed regulator under power mode | |
| CN102279901B (en) | Modeling method specific to third generation pressurized water reactor nuclear power generating unit | |
| CN103311940B (en) | Integrated control method for micro-grid load and energy accumulation | |
| Guo et al. | Hydropower system operation stability considering the coupling effect of water potential energy in surge tank and power grid | |
| Zhu et al. | Setting condition of surge tank based on stability of hydro-turbine governing system considering nonlinear penstock head loss | |
| CN102543232B (en) | Combined method for controlling water level and pressure of voltage stabilizer for nuclear power plant of pressurized water reactor | |
| Ansarifar et al. | Gain scheduled dynamic sliding mode control for nuclear steam generators | |
| CN107679769A (en) | Power system frequency response model method for building up and frequency characteristic index calculating method containing wind-powered electricity generation | |
| WO2022105357A1 (en) | Helium flow control system and method for high temperature gas-cooled reactor having incremental adjustment function | |
| CN103094929A (en) | Method for fast building alternating current and direct current hybrid system small disturbance state-space model | |
| CN104389733A (en) | Water turbine PID (Proportion Integration Differentiation) speed regulator control parameter setting method based on uncertainty model | |
| CN105162164A (en) | Method of building low-order dynamic frequency response model with wind power integration system | |
| Beus et al. | Application of an adaptive model predictive control algorithm on the Pelton turbine governor control | |
| CN104793610A (en) | Method and device for determining parameters of feed forward controller of coordination system | |
| CN114999687B (en) | Nuclear reactor thermal hydraulic transient test electric power adjusting method and system | |
| CN105896538A (en) | Modeling method for auxiliarypower load correction model based on measured data | |
| CN104484528A (en) | Nuclear power unit power and electric hybrid simulation platform based on PSCAD | |
| Yang et al. | Critical stable cross-sectional area of surge tank in hydropower plant with multiple units sharing common hydraulic system | |
| CN105719092A (en) | Analysis method for overall stability of nuclear power unit | |
| CN107134795A (en) | A kind of boilers heated electrically participates in the control system and control method of mains frequency regulation | |
| CN102410138A (en) | Method for acquiring optimal control input of wind generating set | |
| CN106528978A (en) | Dynamic simulation method and system of speed regulating systems of advanced pressurized water reactor nuclear power unit | |
| Wang et al. | Modeling and coordinated control for active power regulation of pumped storage‐battery integrated system under small‐disturbances | |
| CN105140957A (en) | Electromechanical oscillation mode estimation method based on aggregation models of wind power plant and photovoltaic power station |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| C06 | Publication | ||
| PB01 | Publication | ||
| C10 | Entry into substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| C14 | Grant of patent or utility model | ||
| GR01 | Patent grant |