CN117052495A - Nuclear energy heat supply unit stacking power matching method and system - Google Patents
Nuclear energy heat supply unit stacking power matching method and system Download PDFInfo
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F01—MACHINES OR ENGINES IN GENERAL; ENGINE PLANTS IN GENERAL; STEAM ENGINES
- F01K—STEAM ENGINE PLANTS; STEAM ACCUMULATORS; ENGINE PLANTS NOT OTHERWISE PROVIDED FOR; ENGINES USING SPECIAL WORKING FLUIDS OR CYCLES
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F01—MACHINES OR ENGINES IN GENERAL; ENGINE PLANTS IN GENERAL; STEAM ENGINES
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- F01K17/00—Using steam or condensate extracted or exhausted from steam engine plant
- F01K17/02—Using steam or condensate extracted or exhausted from steam engine plant for heating purposes, e.g. industrial, domestic
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
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Abstract
The invention discloses a nuclear energy heat supply unit stacking power matching method and system, comprising the following steps: the first computing unit acquires a first-stage pressure measured value and computes a power deviation of the stacker; the second calculation unit calculates and obtains a machine side power demand value according to the power deviation of the stacker and the first-stage pressure measured value; the matching unit matches the stacker power according to the side power demand value. According to the matching method designed by the invention, the power of the turbo generator set represented by the first-stage pressure is converted into a power demand signal of the reactor on the machine side through a corresponding closed-loop compensation algorithm so as to coordinate the power balance among the reactor machines; the method can be used under the working condition that the steam extraction flow cannot be accurately measured, and the condition that the reactor still meets the requirements of over-power protection and response to transient working conditions under the heating working condition is ensured through the corresponding limiting links.
Description
Technical Field
The invention belongs to the field of nuclear energy heat supply, and particularly relates to a nuclear energy heat supply unit stacking power matching method and system.
Background
The nuclear energy gradually becomes one of the main directions of energy development in the future due to the high-efficiency comprehensive energy utilization rate and renewable energy consumption rate, so that the nuclear power unit operation flexibility is improved for continuously developing the peak shaving potential of the nuclear power unit, and in recent years, nuclear energy heat supply gradually becomes a hot spot for research in the industry. From the study and analysis of the heating scheme of the AP1000 nuclear power unit, it can be seen that nuclear energy heating is gradually changed from small-range heating to multi-user heating, the duty ratio of the heating load in the whole heating load is higher and higher, and the multi-user increases the diversity and uncertainty of the heating load change.
Different from the conventional heat and power cogeneration unit in a heat and power fixed electricity mode, the nuclear power unit is a pumping and condensing unit, so that the operation mode of the back pressure unit is not suitable for the nuclear power unit. After the pure condensing unit is subjected to heat supply transformation, the original pure condensing operation mode is replaced by a part of steam extraction and condensing type cogeneration operation mode. In the cogeneration mode, as the heat supply load is introduced, the first-stage pressure curve of the primary characteristic of the power generation load of the two-loop turbo generator set is corrected by the new two-loop total load (heat supply and power generation) curve, so that a new stack machine coordination control mode is formed. By adopting the first-stage pressure curve correction scheme based on the steam extraction flow, the total load of the two loops cannot be accurately reflected due to the accuracy of flow measurement. Because of the particularities of the nuclear power unit, the construction or transformation period is longer, the planned heat supply and the actual heat supply areas can have larger difference, the nuclear power unit is limited by the heat supply areas, the change ratio of the steam extraction quantity can reach 5-10, the steam extraction quantity is different, and when the thermal load is switched or the unit fails, the unit power is different, and corresponding control and protection measures are different.
The conventional unit adopts a heat supply control method combining load control and pre-unit pressure, is based on the premise that the pre-unit pressure is unchanged, and the conventional unit operates in a fixed-sliding-fixed mode, and during steady-state load operation of the unit, the pre-unit pressure is kept constant, so that coordination and energy balance between the turbo generator unit and a boiler are facilitated, and therefore, the conventional unit adopts a pre-unit pressure control mode. However, the steam pressure of the secondary loop of the nuclear power unit is reduced along with the increase of the nuclear power, so that the pressure before the nuclear power unit is a variable during steady-state operation, and the pressure before the nuclear power unit cannot be directly introduced as a means for load control or power matching of the nuclear power unit. Under the condition that the steam extraction flow cannot be accurately measured, the first-stage pressure requirement value is corrected by introducing a corresponding closed-loop feedback link, so that the balance between the power of the steam turbine generator unit and the power of the nuclear island reactor is a problem to be solved.
Disclosure of Invention
In order to solve the problems, on the one hand, the invention discloses a nuclear energy heat supply unit stacking power matching method, which comprises the following steps:
acquiring a first-stage pressure measured value and calculating power deviation of a reactor;
calculating to obtain a machine side power demand value according to the power deviation of the stacker and a first stage pressure measurement value;
and matching the power of the reactor according to the side power demand value.
Further, calculating the power deviation of the stacker comprises calculating the deviation between the measured value of the electric power of the steam turbine generator unit and the set value of the electric power of the steam turbine generator unit; and the deviation between the turbine generator set electric power measurement and the reactor power.
Further, load adjustment is performed before calculating the deviation between the steam turbine generator unit electric power measured value and the steam turbine generator unit electric power set value, and the load adjustment comprises the following steps:
determining a set value of the electric power of the steam turbine generator unit and obtaining a measured value of the electric power of the steam turbine generator unit;
calculating a first deviation between the set value of the electric power of the steam turbine generator unit and the measured value of the electric power of the steam turbine generator unit;
comparing the first deviation with a load deviation set point; if the first deviation is within the load deviation set value, completing the load adjustment process; if the first deviation exceeds the load deviation set value, circulating until the first deviation is within the load deviation set value.
Further, the clipping operation is performed before the set value of the electric power of the unit is determined:
setting the electric power limit value of the turbo generator set, and when the electric power set value of the turbo generator set is within the set limit value range, enabling the amplitude limiting operation output value to be equal to the electric power of the turbo generator set; and when the set value of the electric power of the steam turbine generator unit exceeds the limit value range, the set value of the electric power of the steam turbine generator unit is not output.
Further, calculating the deviation between the turbo-generator set electric power measurement and the reactor power comprises the steps of:
obtaining a measured value of reactor power and electric power of a steam turbine generator unit;
a stack power bias between the reactor power and the unit electrical power measurements is calculated.
Further, calculating a machine side power demand value from the stack machine power bias and the first stage pressure measurement value includes the steps of:
determining whether to correct the first stage pressure measurement;
if the first-stage pressure measured value needs to be corrected, acquiring the steam extraction flow;
correcting the first-stage pressure measurement value according to the extraction flow and the first-stage pressure approximate correction formula;
calculating a second deviation between the stack machine power deviation and the corrected first stage pressure measurement;
and filtering and limiting the second deviation to obtain a machine side power requirement value.
Further, whether the first-stage pressure measured value is corrected is determined, and the first-stage pressure measured value is determined according to the current working condition of the nuclear power unit:
if the current transient working condition of the nuclear power unit is the steam extraction and heat supply working condition, correcting the first-stage pressure measured value; if the transient working condition of the current nuclear power unit is a pure condensation working condition, the first-stage pressure measured value does not need to be corrected.
On the other hand, the invention also discloses a reactor power matching system of the nuclear energy heat supply unit, which comprises:
the first calculating unit is used for obtaining a first-stage pressure measured value and calculating power deviation of the stacker;
the second calculation unit is used for calculating a machine side power demand value according to the stacker power deviation and the first stage pressure measurement value;
and the matching unit is used for matching the power of the stacker according to the side power demand value.
Further, calculating the power deviation of the stacker comprises calculating the deviation between the measured value of the electric power of the steam turbine generator unit and the set value of the electric power of the steam turbine generator unit; and the deviation between the turbine generator set electric power measurement and the reactor power.
Further, the system further comprises a load adjusting unit, wherein the load adjusting unit is used for adjusting the load before calculating the deviation between the measured value of the electric power of the turbo generator set and the set value of the electric power of the turbo generator set, and specifically comprises the following steps:
determining a set value of the electric power of the steam turbine generator unit and obtaining a measured value of the electric power of the steam turbine generator unit;
calculating a first deviation between the set value of the electric power of the steam turbine generator unit and the measured value of the electric power of the steam turbine generator unit;
comparing the first deviation with a load deviation set point; if the first deviation is within the load deviation set value, completing the load adjustment process; if the first deviation exceeds the load deviation set value, circulating until the first deviation is within the load deviation set value.
Further, the second computing unit is specifically configured to:
determining whether to correct the first stage pressure measurement;
if the first-stage pressure measured value needs to be corrected, acquiring the steam extraction flow;
correcting the first-stage pressure measurement value according to the extraction flow and the first-stage pressure approximate correction formula;
calculating a second deviation between the stack machine power deviation and the corrected first stage pressure measurement;
and filtering and limiting the second deviation to obtain a machine side power requirement value.
Further, whether the first-stage pressure measured value is corrected is determined, and judgment is carried out according to the current working condition of the nuclear power unit:
if the current transient working condition of the nuclear power unit is the steam extraction and heat supply working condition, correcting the first-stage pressure measured value;
if the transient working condition of the current nuclear power unit is a pure condensation working condition, the first-stage pressure measured value does not need to be corrected.
The invention has the beneficial effects that:
according to the matching method designed by the invention, the power of the turbo generator set represented by the first-stage pressure is converted into a power demand signal of the reactor on the machine side through a corresponding closed-loop compensation algorithm so as to coordinate the power balance among the reactor machines; the method can be used under the working condition that the steam extraction flow cannot be accurately measured, and the condition that the reactor still meets the requirements of over-power protection and response to transient working conditions under the heating working condition is ensured through the corresponding limiting links.
The invention can maintain the power balance between the nuclear reactor and the turbo generator set through corresponding closed loop feedback without considering the signal coupling between thermoelectricity under the working condition of steam extraction and heat supply of the set, and maintain the safe and stable operation of the set and the dynamic coordination of the power between the set. The method can be used for heat supply reconstruction of the existing nuclear power unit and newly-built nuclear power heat supply unit.
Additional features and advantages of the invention will be set forth in the description which follows, and in part will be obvious from the description, or may be learned by practice of the invention. The objectives and other advantages of the invention may be realized and attained by the structure particularly pointed out in the written description and claims hereof as well as the appended drawings.
Drawings
In order to more clearly illustrate the embodiments of the present invention or the technical solutions of the prior art, the following description will briefly explain the drawings used in the embodiments or the description of the prior art, and it is obvious that the drawings in the following description are some embodiments of the present invention, and other drawings can be obtained according to these drawings without inventive effort for a person skilled in the art.
FIG. 1 shows a graph of reactor characteristics in an embodiment of the invention;
FIG. 2 shows a graph of electrical load versus first stage pre-pressure in an embodiment of the invention;
FIG. 3 is a graph showing the relationship between the extraction flow and the first stage front pressure at different stack powers in an embodiment of the present invention;
FIG. 4 shows a flow chart for calculating stack machine power bias in an implementation of the invention;
fig. 5 shows a schematic flow chart after the first stage pressure correction and stack power deviation are input under the working condition of steam extraction and heat supply in the embodiment of the invention.
Detailed Description
For the purpose of making the objects, technical solutions and advantages of the embodiments of the present invention more apparent, the technical solutions of the embodiments of the present invention will be clearly and completely described below with reference to the accompanying drawings in the embodiments of the present invention, and it is apparent that the described embodiments are some embodiments of the present invention, but not all embodiments of the present invention. All other embodiments, which can be made by those skilled in the art based on the embodiments of the invention without making any inventive effort, are intended to be within the scope of the invention.
The invention designs a nuclear energy heat supply unit piling machine (namely a turbo generator set and a reactor) power matching method based on the large-scale heat supply planning of the current nuclear power unit, and the method can be used for newly building or technically modifying the nuclear energy heat supply unit. During the power operation of the nuclear power unit, the bypass discharge system is closed, and the power level of the steam turbine generator unit represents the power of the two loops. Under the action of a digital electric control system (DEH) of the turbo generator set, a high-pressure Main Steam Valve (MSV) and a medium-pressure main steam valve (RSV) are kept fully opened, high-pressure regulating valve (GV) and medium-pressure regulating valve (ICV) commands are generally controlled according to a multiple of 1:3, when a load command is about more than 30%, the ICV is kept fully opened and no steam flow regulation is participated, so that load control of more than 30% is generally completed by the DEH through the opening of the GV.
In the steam extraction and heating mode, both thermal and electrical load changes will cause reactor power changes. Due to the running characteristics of the nuclear power unit and the coordination control strategy difference of the reactor, the nuclear power large-scale heat supply unit must fully consider various transient and steady-state working conditions and various influencing factors. For large advanced pressurized water reactor units, a scheme of steady state operation with linear average temperature and power is generally adopted, and the scheme is characterized in that the average temperature of a first loop is increased along with the increase of nuclear power, the steam pressure of a second loop is reduced along with the increase of nuclear power, and the corresponding nuclear reactor characteristic curve is shown in figure 1. In the large-scale steam extraction and heat supply mode, the steam extraction amount of the unit can be more than 20% of the total power of the unit, the heat load is relatively large, the same electric power is used, the first-stage pressure is different under different steam extraction flows, the relation curve between the electric load and the first-stage pressure is shown in fig. 2, and the relation curves of different units are different, which is only exemplified here. Under the working condition of steam extraction and heat supply, the fluid model of the steam turbine generator unit is changed due to the introduction of a steam extraction port, and compared with the pure condensation working condition, the first-stage pressure curve is required to be corrected.
The overall operation mode of the nuclear power unit adopts a 'reactor-to-machine' mode, for the turbo-generator unit, when the regenerative system is normally put into operation and the load is more than 30%, the first-stage inlet pressure of the turbo-generator unit can represent the power of the turbo-generator unit, so that the load power signals of the current operating or building nuclear power unit are represented by the first-stage pressure, and therefore, to ensure the adjustment precision of the power of the reactor, the accuracy of the electric and thermal loads of the nuclear power unit fed back by the first-stage pressure must be ensured.
The influence of the thermal load change process on the power of the steam turbine generator unit is mainly expressed in that: assuming that at a certain moment, the heat load is increased, namely the heat supply steam extraction amount demand is increased, under the condition that the electric load is unchanged, the heat supply steam extraction amount is increased, the steam inlet flow of a low-pressure cylinder is reduced, the effective acting steam amount of the turbo generator set is reduced, the electric power is reduced, the load instruction of the turbo generator set is unchanged, the power closed loop deviation is increased, the load controller drives a control system to open a large GV, the steam inlet flow of the whole turbo generator set is increased, and the acting of the turbo generator set is increased; meanwhile, the first-stage pressure of the turbo generator set is increased, signals are transmitted to a Reactor Coolant System (RCS), and the power of the reactor power regulating system is driven to increase so that the two systems are balanced.
The principle is similar to that of the heat load reduction process, except that the adjustment direction is different. Assuming that at a certain moment, the heat load is reduced, namely the heat supply steam extraction amount is reduced, under the condition that the electric load is unchanged, the heat supply steam extraction amount is reduced, the steam inlet flow of a low-pressure cylinder is increased, the effective working steam amount of the turbo generator set is increased, the electric power is increased, the load instruction of the turbo generator set is unchanged, the power closed loop generates negative deviation, the load controller drives the control system to turn off GV, the steam inlet flow of the whole turbo generator set is reduced, and the work of the turbo generator set is reduced; meanwhile, the first-stage pressure of the steam turbine generator unit is reduced, signals are transmitted to a reactor power adjusting system, and the reactor power adjusting system is driven to reduce power so that the two are balanced.
The electrical load is changed as follows: at a certain moment, under the condition that the reactor power is unchanged, a load instruction is increased, the GV opening is increased, the steam inlet flow of the steam turbine generator unit is increased, the functional capacity of the steam turbine generator unit is increased, the electric power is increased, meanwhile, the first-stage pressure is increased, the steam inlet flow of the low-pressure cylinder and the heat supply steam flow of the steam turbine generator unit are both increased, and when the electric load is reduced, the change situation is opposite.
From the above analysis, the larger the extraction flow, the higher the first stage pressure, the larger the total intake flow of the turbo generator set, and the corresponding reactor power boost, to maintain the two-loop steam requirement. Under the same extraction flow, the higher the electric load is, the higher the first-stage pressure is, the larger the total steam inlet flow of the represented turbo generator set is, and the corresponding reactor power is required to be increased so as to maintain the two-loop steam requirement. Under the working condition of steam extraction and heat supply, under the condition that the bypass discharge system does not act, the power requirement of the two loops is equal to the sum of the heat power required by the electric energy conversion of the steam turbine generator unit and the heat power required by steam extraction and heat supply.
The extraction flow can be measured by a flow device arranged in the extraction loop, and the electric load can introduce a power signal in the original DEH control device.
According to the through-flow model of the turbo generator set, the first-stage pressure can be corrected under different extraction flow rates. Under different reactor powers, the relation curve of the steam extraction flow and the first-stage pressure is shown in fig. 3, and a first-stage pressure approximate correction formula is obtained according to the data accumulated by the simulation curve:
P 0 =p- (0.00599165P-0.00606767) G extraction/346
Wherein P is the first stage pressure measurement, P 0 G is the extraction flow value for the corrected first stage pressure; the correction formula is a function of the extraction flow value G and the first stage pressure measurement value P. The first-stage pressure measurement value P can be measured by means of an instrument measurement technology, the measurement accuracy is about 0.1%, and the corresponding introduced error is negligible. However, because the large pressurized water reactor nuclear generator set is mainly steam with wet saturated steam, according to economic analysis, the heat supply steam is generally taken from a steam exhaust pipeline between a high-pressure cylinder and a steam-water separation reheater, the humidity of the steam extraction heat supply steam is changed between about 10% and 14%, the forms of the steam-liquid two-phase flow of the wet steam are different flow states along with the change of the humidity or the flow rate of the steam, meanwhile, the complexity of the flow of the wet steam, the complexity of the form of water drops and the process of heat transfer and phase change are simultaneously carried out in the flowing process, and the factors give the wet state of the wet steamThe degree and flow measurement also brings great difficulty, and even if a special steam-water two-phase flow measurement technology is adopted, the mass flow error is still +/-5%; and the presence of the liquid phase makes the actual measured pressure difference high. Therefore, based on the existing flow measurement technology, the flow measurement cannot be accurately completed, and the error of the extraction flow value G in the correction formula is larger, so that the corrected first-stage pressure is also caused to have larger error.
For the above reasons, the use of the directly corrected first stage pressure curve to represent the power at the two loop side introduces a large control error, and we propose a first stage pressure correction scheme for the power demand at the reactor side, as shown in fig. 4.
The matching method provided by the invention mainly comprises two parts:
the first part calculates the power deviation of the stacker in steady state
As shown in fig. 4, calculating the stack machine power deviation at steady state includes the steps of:
(1) The load adjustment process judgment unit includes the following parts:
the turbine generator set electric power set value unit: the set value of the electric power of the steam turbine generator unit is manually set by a unit DEH control system through a man-machine interface, and in an automatic mode, the set value of the electric power of the steam turbine generator unit is completed and automatically made to approach the set value of the electric power of the steam turbine generator unit according to the set change rate after being executed according to GO.
An electric power limiting link of the turbo generator set: under the heat supply and steam extraction working conditions, the electric power rate of the steam turbine generator unit cannot reach 100% of rated power, so that the limit value of the electric power of the steam turbine generator unit needs to be set, and the reactor is prevented from being operated under the over-power condition, wherein the limit value comprises a high limit or a low limit; when the set value of the electric power of the turbo generator set is in the set high limit or low limit range, the output value of the limiting link is equal to the set value of the electric power of the turbo generator set; when the set value of the electric power of the steam turbine generator unit exceeds the set high limit or low limit, the electric power is not output;
measurement value of electric power of steam turbine generator unit: from the on-site power meter, the signal is accessed into the set DEH for power control.
Subtractor unit: the subtracter unit compares the deviation between the set value of the electric power of the steam turbine generator unit and the measured value of the electric power of the steam turbine generator unit, defines the deviation at the moment as the first deviation of the steam turbine generator unit so as to determine whether the load adjustment process is finished, and when the set value of the electric power of the steam turbine generator unit is equal to the measured value of the electric power of the steam turbine generator unit, the load adjustment is finished.
The subtracter outputs a first deviation, the first deviation is calculated by the ABS absolute value calculation unit, and then enters the high-low limit unit, and the high-low limit unit sets a load deviation set value according to the load control precision; in the embodiment of the invention, the load deviation set value is set to be 0.02%, but is not limited to be 0.02%. If the load deviation is within 0.02%, the load adjustment process is judged to be completed, the corresponding gating link output is true, and if the load deviation is greater than 0.02%, the cycle waits until the load deviation is within 0.02%.
(2) Pile machine power deviation calculating unit
The reactor power is from the interface signal of the nuclear island, compare the deviation between electric power measured value of the turbo generator set and reactor power through the subtracter, define the deviation between the two as the power deviation of the reactor; the power deviation of the reactor characterizes that the two loop power requirement values and the actual power of the reactor are different, namely, the first-stage pressure correction value of the two loop is characterized that the two loop power requirement values and the actual power requirement are different, so that the first-stage pressure value needs to be corrected correspondingly, and if the power deviation of the reactor is 0, the first-stage pressure value does not need to be corrected.
Linear transformation link K: the input/output is in a linear relation, K is used for adjusting the magnitude of the deviation value, and is 1 under normal working conditions without adjustment; if the system or equipment characteristics change and the seasonal change cause the temperature/back pressure of the circulating cooling water to change, the power deviation of the stacker can be correspondingly adjusted through the conversion coefficient, so that the first-stage pressure compensation intensity is adjusted. In the embodiment of the invention, the input is the difference value (output of a subtracter) between the electric power measured value of the steam turbine generator unit and the reactor power, and the output is the power deviation of the adjusted reactor, as shown in fig. 4 and 5.
And the second part is used for judging whether the nuclear power unit is in a steam extraction and heat supply working condition or not, and inputting the first-stage pressure correction and stack power deviation compensation under the steam extraction and heat supply working condition. As shown in fig. 5, the method specifically includes:
(1) First stage pressure correction
First stage pressure measurement: meter signals from the field.
Pure condensing condition or transient condition judging unit: the working condition when the unit supplies heat is not input, namely the pure condensing working condition comprises the working condition that the heat is not input or the heat is removed, and under the working condition, the working condition of the nuclear power heat supply unit is unchanged compared with the original design, so that the first-stage pressure measured value is not corrected.
Extraction flow rate: and correcting the first-stage pressure measured value according to a first-stage pressure approximate correction formula according to the extraction flow under the heat supply working condition by using a signal from a field instrument.
Specifically, the first-stage pressure approximation correction equation is typically provided after calculation by the turbine plant through a fluid model. The extraction flow can be measured by a flow device installed in the extraction circuit.
In one embodiment, a first-order pressure approximation correction equation is derived from the data accumulated in the simulation curve:
wherein P is the first stage pressure measurement, P 0 G is the extraction flow value for the corrected first stage pressure; however, the above formulas are only exemplary, and are not limited to the listed coefficient values, and the coefficient values need to be adjusted according to the heat balance test when the heat balance test is applied to different units.
(2) Transient state working condition discriminating unit
When any working condition such as Overspeed Protection (OPC) action of a steam turbine, tripping of the steam turbine, manual cutting of heat supply, rapid load reduction RB, critical water level at the side of a heat exchanger, full stop of a circulating water pump, overrun of steam extraction flow, overrun of high discharge pressure, tripping of the steam turbine and the like occurs, heat supply is cut off, and the steam turbine generator unit resumes operation under a pure condensation working condition.
(3) Machine side power demand calculation unit
Pile machine power deviation: from the first part algorithm output.
And (3) filtering: band-pass filtering to eliminate disturbance and compensate the lead and lag of link.
Flow limiting link: limiting the first-stage pressure amplitude, and preventing the main steam flow of the unit from being too large, thereby causing the super power of the unit.
After the first-stage pressure measured value is corrected and overlapped with the power deviation of the stacker, the difference value between the corrected first-stage pressure value and the power deviation of the stacker is calculated through a subtracter, the deviation value between the corrected first-stage pressure value and the power deviation of the stacker is defined as a second deviation, the second deviation is subjected to a corresponding filtering link and a flow limiting link to obtain a final machine side power required value, and the machine side power required value is transmitted to a nuclear island power regulating system, so that the final balance of the power of the stacker and the power of the stacker is promoted.
For example, if the flow of the steam extraction becomes larger at a certain moment, under the condition that the power is not increased by the nuclear reactor, the generated energy becomes smaller, the second deviation generates positive deviation, so that the power of the reactor is increased, the first deviation, namely, the positive deviation is generated between the electric power setting and the actual power, the main regulating gate of the steam turbine generator unit is opened, the generated energy is increased, the first deviation is reduced, a regulating process is started, if the first deviation is smaller than 0.02%, the reactor power and the two-loop power (namely, the power occupied by the steam turbine generator unit and the steam extraction flow) are considered to be balanced, the regulating process is ended, a gating link is stopped at the moment, the output of a linear link K, namely, the deviation of the electric power measured value of the unit after adjustment and the power of the reactor is overlapped on a first-stage pressure correction f (x), the regulated-stage pressure correction value is considered to be overlapped with the deviation value of the gating, so that the main regulating gate is not changed any more, the main regulating gate is transmitted to a nuclear island power control system, and the whole control concept is that the nuclear island power and the nuclear power and the two-loop power value and the two-phase power value can be balanced in the regulating process is selected from a plurality of dynamic values in the regulating process.
The matching method designed by the invention converts the power of the turbo generator set represented by the first-stage pressure into a power demand signal of the reactor on the machine side through a corresponding closed-loop compensation algorithm so as to coordinate the power balance between the nuclear reactor and the turbo generator set. The algorithm can be used under the working condition that the steam extraction flow cannot be accurately measured, and the condition that the nuclear reactor still meets the super-power protection and the response to the transient working condition under the heating working condition is ensured through the corresponding limiting links.
The matching method provided by the invention is suitable for large-scale heat supply nuclear power units, namely, heat supply nuclear power units with heat supply steam extraction accounting for 10% or more of rated power generation of the units, when the steam extraction of the steam turbine generator unit is too low, a pure condensation curve is adopted or only the first-stage pressure measurement value is simply corrected, and because the steam extraction share accounts for lower power generation proportion, the measurement difference of the steam extraction flow has less influence on the power matching of the reactor.
When the matching method provided by the invention is applied to a technical improvement project, the whole framework of the original control system is not changed, the power control of the steam turbine generator unit is still realized by the unit liquid control system DEH, and the first-stage pressure measured value is directly transmitted to the nuclear island power control system for representing the power requirement of the two loops; after the heat supply is modified, the measured value of the first-stage pressure is required to be introduced into a DEH control system, after correction and power compensation, an AO signal is generated by the DEH control system and is transmitted to a nuclear island power control system, and the total power requirement of the two loops is represented, namely, the original on-site instrument signal is changed into a control system inter-station signal.
In addition, because the extraction flow value is generally virtual and high, the corrected first-stage pressure is low, when the actual system operates near rated power, the initial demand value of reactor power is generally high because the accumulation deviation unit compensates only in steady state, the heat supply control system has correspondingly limited the demand value through the flow limiting unit of the turbo generator set, and the power control system on the side of the nuclear island can correspondingly perform over-limit protection on the power on the side of the nuclear island when the condition exists.
Although the invention has been described in detail with reference to the foregoing embodiments, it will be understood by those of ordinary skill in the art that: the technical scheme described in the foregoing embodiments can be modified or some technical features thereof can be replaced by equivalents; such modifications and substitutions do not depart from the spirit and scope of the technical solutions of the embodiments of the present invention.
Claims (12)
1. The nuclear energy heat supply unit stacking power matching method is characterized by comprising the following steps of:
acquiring a first-stage pressure measured value and calculating power deviation of a reactor;
calculating to obtain a machine side power demand value according to the power deviation of the stacker and a first stage pressure measurement value;
and matching the power of the reactor according to the side power demand value.
2. The method of matching of claim 1, wherein calculating the stack power deviation comprises calculating a deviation between a turbo-generator set electrical power measurement and a turbo-generator set electrical power setpoint; and the deviation between the turbine generator set electric power measurement and the reactor power.
3. The matching method according to claim 2, characterized in that load adjustment is performed before calculating the deviation between the turbo-generator-unit electric power measurement and the turbo-generator-unit electric power set point, the load adjustment comprising the steps of:
determining a set value of the electric power of the steam turbine generator unit and obtaining a measured value of the electric power of the steam turbine generator unit;
calculating a first deviation between the set value of the electric power of the steam turbine generator unit and the measured value of the electric power of the steam turbine generator unit;
comparing the first deviation with a load deviation set point; if the first deviation is within the load deviation set value, completing the load adjustment process; if the first deviation exceeds the load deviation set value, circulating until the first deviation is within the load deviation set value.
4. A matching method according to claim 3, characterized in that the clipping operation is performed before the set-point of the unit electric power is determined:
setting the electric power limit value of the turbo generator set, and when the electric power set value of the turbo generator set is within the set limit value range, enabling the amplitude limiting operation output value to be equal to the electric power of the turbo generator set; and when the set value of the electric power of the steam turbine generator unit exceeds the limit value range, the set value of the electric power of the steam turbine generator unit is not output.
5. The matching method according to claim 2, wherein,
calculating the deviation between the turbine generator set electric power measurement and the reactor power comprises the following steps:
obtaining a measured value of reactor power and electric power of a steam turbine generator unit;
a stack power bias between the reactor power and the unit electrical power measurements is calculated.
6. The matching method according to any one of claims 1 to 5, wherein,
the machine side power demand value is calculated according to the stack machine power deviation and the first stage pressure measured value, and comprises the following steps:
determining whether to correct the first stage pressure measurement;
if the first-stage pressure measured value needs to be corrected, acquiring the steam extraction flow;
correcting the first-stage pressure measurement value according to the extraction flow and the first-stage pressure approximate correction formula;
calculating a second deviation between the stack machine power deviation and the corrected first stage pressure measurement;
and filtering and limiting the second deviation to obtain a machine side power requirement value.
7. The matching method according to claim 6, wherein,
determining whether to correct the first-stage pressure measurement value, and determining according to the current working condition of the nuclear power unit:
if the current transient working condition of the nuclear power unit is the steam extraction and heat supply working condition, correcting the first-stage pressure measured value; if the transient working condition of the current nuclear power unit is a pure condensation working condition, the first-stage pressure measured value does not need to be corrected.
8. A nuclear heating unit stacker power matching system, the system comprising:
the first calculating unit is used for obtaining a first-stage pressure measured value and calculating power deviation of the stacker;
the second calculation unit is used for calculating a machine side power demand value according to the stacker power deviation and the first stage pressure measurement value;
and the matching unit is used for matching the power of the stacker according to the side power demand value.
9. The matching system of claim 8, wherein the matching system is configured to match the matching system,
the step of calculating the power deviation of the stack machine comprises calculating the deviation between the measured value of the electric power of the steam turbine generator unit and the set value of the electric power of the steam turbine generator unit; and the deviation between the turbine generator set electric power measurement and the reactor power.
10. Matching system according to claim 8 or 9, characterized in that the system further comprises a load adjustment unit for load adjustment prior to calculating the deviation between the turbo-generator-unit electric power measurement and the turbo-generator-unit electric power set point, in particular comprising:
determining a set value of the electric power of the steam turbine generator unit and obtaining a measured value of the electric power of the steam turbine generator unit;
calculating a first deviation between the set value of the electric power of the steam turbine generator unit and the measured value of the electric power of the steam turbine generator unit;
comparing the first deviation with a load deviation set point; if the first deviation is within the load deviation set value, completing the load adjustment process; if the first deviation exceeds the load deviation set value, circulating until the first deviation is within the load deviation set value.
11. The matching system of claim 8, wherein the matching system is configured to match the matching system,
the second computing unit is specifically configured to:
determining whether to correct the first stage pressure measurement;
if the first-stage pressure measured value needs to be corrected, acquiring the steam extraction flow;
correcting the first-stage pressure measurement value according to the extraction flow and the first-stage pressure approximate correction formula;
calculating a second deviation between the stack machine power deviation and the corrected first stage pressure measurement;
and filtering and limiting the second deviation to obtain a machine side power requirement value.
12. The matching system of claim 11, wherein the determination of whether to correct the first stage pressure measurement is based on a current operating condition of the nuclear power unit:
if the current transient working condition of the nuclear power unit is the steam extraction and heat supply working condition, correcting the first-stage pressure measured value;
if the transient working condition of the current nuclear power unit is a pure condensation working condition, the first-stage pressure measured value does not need to be corrected.
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