CN117854785A - Method, device, equipment and medium for determining unit output of nuclear power station - Google Patents
Method, device, equipment and medium for determining unit output of nuclear power station Download PDFInfo
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Abstract
The invention discloses a method, a device, equipment and a medium for determining the unit output of a nuclear power station, wherein the method for determining the unit output of the nuclear power station comprises the following steps: under the condition that the nuclear power station is in a first operation condition, determining the actual heat load parameter of the first condenser and the heat load parameter of the second condenser; determining a first unit output value of the nuclear power station according to the actual heat load parameter of the first condenser and the actual heat load parameter of the second condenser; determining an actual heat load parameter of the third condenser and a heat load parameter of the second condenser under the condition that the nuclear power station is in a second operation condition; determining a second unit output value of the nuclear power station according to the third condenser actual heat load parameter and the second condenser actual heat load parameter; and determining a change curve of the unit output according to the first unit output value, the second unit output value and the operation condition parameters of the nuclear power station. By the technical scheme, the unit output can be operated according to the optimal output, and the Internet power quantity and the power plant benefit are improved.
Description
Technical Field
The invention relates to the technical field of nuclear power units, in particular to a unit output determining method, device, equipment and medium of a nuclear power station.
Background
In a nuclear power plant, 3 circulating water pumps are arranged in parallel in summer, 2 circulating water pumps are arranged in parallel in non-summer, if only one circulating water pump is left to run when the nuclear power plant breaks down, circulating water flow greatly decreases, the heat load capacity of a condenser is taken away by circulating water, the vacuum pressure of the condenser increases, the output of the unit decreases, and the output value of the unit needs to be reduced to 40% or below immediately according to the loss of running management program of the circulating water.
In the prior art, a change rule of the output value of the unit under the operation of a single circulating water pump is not given, and the output of the unit obviously has great difference under the operation of the single circulating water pump in summer and non-summer, if the single circulating water pump is required to operate for a long time, the output value of the unit is maintained at 40%, so that the output of the unit does not operate according to the optimal output, the power quantity of surfing the internet is reduced, and the benefit of a power plant is reduced.
Disclosure of Invention
The invention provides a method, a device, equipment and a medium for determining unit output of a nuclear power station, which are used for determining a change curve of unit output when a single circulating water pump operates.
According to an aspect of the present invention, there is provided a unit output determining method of a nuclear power plant, the method including:
under the condition that the nuclear power station is in a first operation condition, determining an actual heat load parameter of a first condenser according to an actual vacuum pressure parameter of the condenser, and determining an actual heat load parameter of a second condenser according to a saturation temperature parameter of the condenser;
determining a first unit output value of the nuclear power station according to the first condenser actual heat load parameter and the second condenser actual heat load parameter;
under the condition that the nuclear power station is in a second operation condition, determining an actual thermal load parameter of a third condenser according to a nuclear island thermal power parameter of the nuclear power station, and determining the actual thermal load parameter of the second condenser;
determining a second unit output value of the nuclear power station according to the third condenser actual heat load parameter and the second condenser actual heat load parameter;
and determining a change curve of the unit output according to the first unit output value, the second unit output value and the operation condition parameters of the nuclear power station.
According to another aspect of the present invention, there is provided a unit output determining apparatus of a nuclear power plant, the apparatus including:
The first operation working condition module is used for determining the actual heat load parameter of the first condenser according to the actual vacuum pressure parameter of the condenser and determining the actual heat load parameter of the second condenser according to the saturation temperature parameter of the condenser under the condition that the nuclear power station is in the first operation working condition;
the first unit output module is used for determining a first unit output value of the nuclear power station according to the first condenser actual heat load parameter and the second condenser actual heat load parameter;
the second operation working condition module is used for determining the actual heat load parameter of the third condenser according to the heat power parameter of the nuclear island of the nuclear power station and determining the actual heat load parameter of the second condenser under the condition that the nuclear power station is in the second operation working condition;
the second unit output module is used for determining a second unit output value of the nuclear power station according to the third condenser actual thermal load parameter and the second condenser actual thermal load parameter;
and the curve determining module is used for determining a change curve of the unit output according to the first unit output value, the second unit output value and the operation condition parameters of the nuclear power station.
According to another aspect of the present invention, there is provided an electronic apparatus including:
At least one processor; and
a memory communicatively coupled to the at least one processor; wherein,
the memory stores a computer program executable by the at least one processor to enable the at least one processor to perform the method of determining the plant output of a nuclear power plant according to any one of the embodiments of the present invention.
According to another aspect of the present invention, there is provided a computer readable storage medium storing computer instructions for causing a processor to implement the method for determining a plant output of a nuclear power plant according to any embodiment of the present invention when executed.
According to the technical scheme provided by the embodiment of the invention, the unit output value of the nuclear power station under the first working condition and the second working condition is determined, so that the change curve of the unit output of the nuclear power station under the single circulating water pump is determined, the situation that the unit output of the nuclear power station is not required to be maintained at 40% under the long-term operation of the single circulating water pump is realized, and the unit output of the nuclear power station is dynamically adjusted according to the seawater temperature, so that the unit output of the nuclear power station operates according to the optimal output, and the Internet surfing electric quantity and the power plant benefit are improved.
It should be understood that the description in this section is not intended to identify key or critical features of the embodiments of the invention or to delineate the scope of the invention. Other features of the present invention will become apparent from the description that follows.
Drawings
In order to more clearly illustrate the technical solutions of the embodiments of the present invention, the drawings required for the description of the embodiments will be briefly described below, and it is apparent that the drawings in the following description are only some embodiments of the present invention, and other drawings may be obtained according to these drawings without inventive effort for a person skilled in the art.
Fig. 1 is a flowchart of a method for determining a unit output of a nuclear power plant according to a first embodiment of the present invention;
fig. 2 is a flowchart of a method for determining a unit output of a nuclear power plant according to a second embodiment of the present invention;
fig. 3 is a schematic structural diagram of a unit output determining device of a nuclear power plant according to a third embodiment of the present invention;
fig. 4 is a schematic structural diagram of an electronic device for implementing a unit output determining method of a nuclear power station according to an embodiment of the present invention.
Detailed Description
In order that those skilled in the art will better understand the present invention, a technical solution in the embodiments of the present invention will be clearly and completely described below with reference to the accompanying drawings in which it is apparent that the described embodiments are only some embodiments of the present invention, not all embodiments. All other embodiments, which can be made by those skilled in the art based on the embodiments of the present invention without making any inventive effort, shall fall within the scope of the present invention.
It should be noted that the terms "first," "second," and the like in the description and the claims of the present invention and the above figures are used for distinguishing between similar objects and not necessarily for describing a particular sequential or chronological order. It is to be understood that the data so used may be interchanged where appropriate such that the embodiments of the invention described herein may be implemented in sequences other than those illustrated or otherwise described herein. Furthermore, the terms "comprises," "comprising," and "having," and any variations thereof, are intended to cover a non-exclusive inclusion, such that a process, method, system, article, or apparatus that comprises a list of steps or elements is not necessarily limited to those steps or elements expressly listed but may include other steps or elements not expressly listed or inherent to such process, method, article, or apparatus.
Example 1
Fig. 1 is a flowchart of a method for determining a unit output of a nuclear power plant according to an embodiment of the present invention, where the method may be performed by a unit output determining device of the nuclear power plant, and the unit output determining device of the nuclear power plant may be implemented in hardware and/or software, and the unit output determining device of the nuclear power plant may be configured in various general-purpose computing devices. As shown in fig. 1, the method includes:
s110, under the condition that the nuclear power station is in a first operation working condition, determining an actual heat load parameter of a first condenser according to an actual vacuum pressure parameter of the condenser, and determining an actual heat load parameter of a second condenser according to a saturation temperature parameter of the condenser.
The heat power of a nuclear island in the nuclear power station under the first operation condition can be in a full power state, and the parameter value of the actual vacuum pressure parameter of a condenser in the nuclear power station can be smaller than or equal to an alarm threshold value. It should be noted that, during the operation of the nuclear power plant, all parameters that can affect the operation of the nuclear power plant in the nuclear power plant are the operation condition parameters of the nuclear power plant. Alternatively, the alarm threshold may be adaptively set according to those skilled in the art, and exemplary, the alarm threshold may be set to 13.3Kpa.
The actual vacuum pressure parameter may refer to a vacuum pressure parameter of a condenser in the nuclear power plant when the nuclear power plant is in operation, and the unit of the actual vacuum pressure parameter is Kpa.
The first condenser actual thermal load parameter may refer to thermal power generated by a nuclear reactor in the nuclear power plant under the first operating condition, with a unit of MWt.
The saturation temperature parameter may be a parameter corresponding to the vacuum pressure parameter, and it should be noted that when the condenser has a parameter value of an actual vacuum pressure parameter, there will be a parameter value of a saturation temperature parameter corresponding to the actual vacuum pressure parameter, and the unit of the saturation temperature parameter is ℃. Optionally, there is a fixed conversion relationship between the parameter value of the saturation temperature parameter and the parameter value of the vacuum pressure parameter.
The actual heat load parameter of the second condenser may refer to the heat output power of a steam generator in the nuclear power plant, with the unit being MWt. Optionally, based on a heat balance principle in the nuclear power station, an equivalent relationship exists between the actual heat load parameter of the first condenser and the actual heat load parameter of the second condenser.
Specifically, under the condition that the nuclear power station is in a first operation condition, the actual heat load parameter of the first condenser in the nuclear power station can be determined according to the actual vacuum pressure parameter of the condenser in the nuclear power station, and then the actual heat load parameter of the second condenser in the nuclear power station can be determined according to the saturation temperature parameter of the condenser.
S120, determining a first unit output value of the nuclear power station according to the actual heat load parameter of the first condenser and the actual heat load parameter of the second condenser.
The first unit output value may be unit output of the nuclear power station under a first operation condition, and the unit is MWe.
Specifically, a first unit output value of the nuclear power plant under a first operating condition may be determined according to the determined actual heat load parameter of the first condenser and the determined actual heat load parameter of the second condenser under the first operating condition of the nuclear power plant.
S130, under the condition that the nuclear power station is in the second operation working condition, determining an actual thermal load parameter of the third condenser according to the nuclear island thermal power parameter of the nuclear power station, and determining the actual thermal load parameter of the second condenser.
The actual vacuum pressure parameter value of the condenser in the nuclear power station under the second operation condition can be larger than the alarm threshold value. It should be noted that, when the nuclear power plant is in the second operation condition, the single circulating water pump cannot lead out all heat loads of the condenser, at this time, the heat power parameter of the nuclear island needs to be reduced, so that the actual vacuum pressure parameter of the condenser is maintained at 13.3KPa, that is, the heat power parameter of the nuclear island needs to be dynamically adjusted when the nuclear power plant is in the second operation condition, so that the actual vacuum pressure parameter of the condenser is maintained at the alarm threshold.
The actual thermal load parameter of the third condenser may be thermal power generated by a nuclear reactor in the nuclear power plant under the second operation condition, and the unit is MWt. Optionally, based on a heat balance principle in the nuclear power plant, an equivalent relationship exists between the actual heat load parameter of the third condenser and the actual heat load parameter of the second condenser.
Specifically, under the condition that the nuclear power station is in the second operation working condition, determining the actual thermal load parameter of the third condenser of the nuclear power station under the second operation working condition according to the thermal power parameter of the nuclear island in the nuclear power station, and determining the actual thermal load parameter of the second condenser of the nuclear power station under the second operation working condition.
And S140, determining a second unit output value of the nuclear power station according to the third condenser actual heat load parameter and the second condenser actual heat load parameter.
The second unit output value may be unit output of the nuclear power station under a second operation condition, and the unit is MWe.
Specifically, the unit output of the nuclear power station under the second operation condition can be determined according to the determined actual heat load of the third condenser and the determined actual heat load of the second condenser when the nuclear power station is under the second operation condition.
Alternatively, in the implementation of the present invention, the at least one unit output value of the nuclear power plant in the first operating condition and the second operating condition may be determined. For example, at least one unit output value of the nuclear power plant under the first operating condition and the second operating condition may be obtained by adjusting operating condition parameters (e.g., sea water temperature, etc.) of the nuclear power plant other than the operating condition parameters related to the first operating condition and the second operating condition.
S150, determining a change curve of the unit output according to the first unit output value, the second unit output value and the operation condition parameters of the nuclear power station.
The operating condition parameter may be a parameter affecting the operation of the nuclear power plant. It should be noted that, in the embodiment of the present invention, in the process of determining the variation curve of the output of the participating unit, the operation condition parameters of the obtained nuclear power station are all obtained under the first operation condition or the second operation condition. For example, in the embodiment of the present invention, the operating condition parameter of the nuclear power plant involved in the process of determining the change curve of the unit output may be the sea water temperature.
Specifically, a change curve of the unit output along with the seawater temperature in the nuclear power station can be determined according to a first unit output value of the nuclear power station under a first operation condition, a second unit output value of the nuclear power station under a second operation condition and operation condition parameters of the nuclear power station.
Optionally, determining a change curve of the unit output according to the first unit output value, the second unit output value and the operation condition parameter of the nuclear power station includes: and performing data fitting on the unit output of the nuclear power station determined by the first unit output value and the second unit output value of the nuclear power station and the sea water temperature parameter value in the nuclear power station to determine the change condition of the unit output of the nuclear power station along with the sea water temperature.
Specifically, data fitting is performed on a unit output value of the nuclear power station under a first operation condition, a unit output value of the nuclear power station under a second operation condition and a seawater temperature parameter value under the first operation condition or the second operation condition, so as to determine a change curve of the unit output of the nuclear power station along with the change condition of the seawater temperature. Alternatively, the data fitting may be performed by a least squares method.
Alternatively, the change curve of the unit output with the sea water temperature in the nuclear power station can be expressed by the following formula:
wherein E is the unit output in the nuclear power station, and T is the sea water temperature.
The change curve of the unit output along with the seawater temperature under the operation of the single circulating water pump of the nuclear power station is determined, the condition that the unit output value of the nuclear power station is maintained at a 40% output value under the operation of the single circulating water pump is avoided, the unit output is operated according to the optimal output by adjusting the seawater temperature, and the Internet surfing electric quantity and the power plant benefit are improved.
According to the technical scheme provided by the embodiment of the invention, the unit output value of the nuclear power station under the first working condition and the second working condition is determined, so that the change curve of the unit output of the nuclear power station under the single circulating water pump is determined, the situation that the unit output of the nuclear power station is not required to be maintained at 40% under the long-term operation of the single circulating water pump is realized, and the unit output of the nuclear power station is dynamically adjusted according to the seawater temperature, so that the unit output of the nuclear power station operates according to the optimal output, and the Internet surfing electric quantity and the power plant benefit are improved.
Example two
Fig. 2 is a flowchart of a unit output determining method of a nuclear power station according to a second embodiment of the present invention, where the present embodiment is an alternative scheme provided on the basis of the foregoing embodiment. It should be noted that, in the embodiments of the present invention, the details of the description of other embodiments may be referred to, and will not be described herein. As shown in fig. 2, the method includes:
s210, under the condition that the nuclear power station is in a first operation working condition, determining a first unit output parameter according to an actual vacuum pressure parameter of the condenser, and determining an actual heat load parameter of the first condenser according to the first unit output parameter.
The first unit output parameter can be determined through a condenser vacuum pressure correction curve and can be used for determining a first unit output value.
Specifically, when the nuclear power station is in the first operating condition, a vacuum pressure correction coefficient of the condenser can be determined according to an actual vacuum pressure parameter of the condenser, a first unit output parameter is determined according to the vacuum pressure correction coefficient, and after the first unit output parameter is determined, an actual heat load parameter of the first condenser can be determined according to the first unit output parameter.
Alternatively, the first unit output parameter may be expressed by the following formula:
E 1 ＝E * /(1+C o1 /100)×(1+C o2 /100)；
C o2 ＝0.004571×P S 4 +0.142×P S 3 -1.581×P S 2 +6.45×P S -8.459；
wherein E is 1 For the first unit to output, E * Is the standard unit output of the nuclear power station, C o1 C is the vacuum correction coefficient of the first condenser o2 Is the vacuum correction coefficient of the second condenser,is the standard vacuum pressure parameter of the condenser, P S Is the actual vacuum pressure parameter of the condenser.
Optionally, in the embodiment of the present invention, under the condition that the nuclear power plant is in the first operating condition, the output value of the standard unit of the nuclear power plant and the parameter value of the standard vacuum pressure parameter of the condenser are fixed values, and may be adaptively set according to those skilled in the art.
Alternatively, the actual heat load parameter of the first condenser may be represented by the following formula:
wherein Q is 1 Is the actual heat load of the first condenser,for nuclear island thermal power, +.>Is mainly the heat quantity carried by the water supply pump group, delta Q * E is the heat load loss of the condenser 1 And outputting force for the first unit.
Optionally, in the embodiment of the present invention, under the condition that the nuclear power station is in the first operating condition, the thermal power of the nuclear island may be a full power value, and the heat value brought by the main water supply pump set and the heat load loss value of the condenser are fixed values, which may be adaptively set by those skilled in the art.
S220, determining a logarithmic average temperature difference parameter of the condenser according to the saturated temperature parameter of the condenser, and determining an actual heat load parameter of the second condenser according to the logarithmic average temperature difference parameter.
The logarithmic average temperature difference parameter can be an index used in the condenser and used for describing the heat transfer effect.
Specifically, the logarithmic average temperature difference parameter of the condenser can be determined through the saturated temperature parameter of the condenser, and the actual heat load parameter of the second condenser is determined according to the determined logarithmic average temperature difference parameter.
Alternatively, the actual heat load parameter of the second condenser may be represented by the following formula:
Q 2 ＝U×A 0 ×LMTD；
LMTD＝(T2-T1)/ln((Ts-T1)/(Ts-T2))；
wherein Q is 2 The actual heat load of the second condenser is U is the total heat transfer coefficient of the condenser, A 0 The heat transfer area of the condenser is LMTD, the logarithmic average temperature difference is T2, the temperature of the circulating water outlet is T1, the temperature of the circulating water inlet is T1, and the saturation temperature parameter is Ts.
Optionally, in the embodiment of the present invention, the circulating water inlet temperature and the condenser heat transfer area have only fixed values, which can be adaptively set according to those skilled in the art.
Alternatively, the total heat transfer coefficient of the condenser can be determined by the total thermal resistance of the nuclear power plant, and the formula is as follows:
U＝1/R；
wherein U is the total heat transfer coefficient of the condenser, and R is the total thermal resistance of the nuclear power station.
Optionally, the total thermal resistance of the nuclear power plant may include a shell side thermal resistance, a pipe wall thermal resistance, a dirt thermal resistance, a pipe side thermal resistance, and the like, and the total thermal resistance of the nuclear power plant may be determined by the following formula:
R＝R s +R m +R f +R t ×(D o /D i )；
R t ＝1/(0.0158×m×Re 0.835 ×Pr 0.462 /D i )；
wherein R is the total thermal resistance of the nuclear power station, R s R is the actual shell side thermal resistance m R is the actual pipe wall heat resistance f For practical fouling resistance, R r For actual tube side thermal resistance, D o For the outer diameter of the heat-transfer tube, D i Is in the heat transfer tubeDiameter, m is the coefficient of thermal conductivity of seawater at the tube side, re is the Reynolds number at the tube side, pr is the Plantaginess number at the tube side,is a standard shell side thermal resistance->For the standard heat load of the first condenser, Q 1 Mu, the actual heat load of the first condenser * The dynamic viscosity of the normal desalted water is mu, the dynamic viscosity of the actual desalted water is mu, k is the heat conductivity coefficient of the actual desalted water, k * Is the heat conductivity coefficient of standard desalted water, ρ is the actual desalted water density, ρ * Is the standard desalted water density.
Optionally, the standard shell side thermal resistance, the standard heat load of the first condenser, the standard demineralized water dynamic viscosity, the standard demineralized water heat conductivity coefficient and the standard demineralized water density are fixed values. It should be noted that, the actual thermal resistance of dirt is related to the coefficient of cleanliness of the heat transfer tube, the coefficient of cleanliness of the heat transfer tube is unchanged, the actual thermal resistance of dirt is a fixed value, the actual thermal resistance of tube wall is related to the material of the heat transfer tube, the material of the heat transfer tube is unchanged, and the actual thermal resistance of tube wall is a fixed value.
S230, determining a circulating water temperature rising parameter of the condenser according to the actual heat load parameter of the first condenser, and determining a circulating water outlet temperature parameter of the condenser in the actual heat load parameter of the second condenser according to the circulating water temperature rising parameter.
The circulating water temperature rise parameter can be used for representing the temperature difference of circulating water entering and exiting the condenser.
The circulating water outlet temperature parameter is used for representing the temperature of circulating water flowing out of the condenser.
Specifically, the temperature rise temperature parameter of the circulating water of the condenser can be determined according to the determined actual heat load parameter of the first condenser when the nuclear power station is in the first operation condition, and the temperature parameter of the circulating water outlet in the determined actual heat load parameter of the second condenser when the nuclear power station is in the first operation condition can be determined according to the determined temperature rise temperature parameter of the circulating water.
Alternatively, the circulating water outlet temperature parameter may be expressed by the following formula:
T2＝T1+ΔT；
ΔT＝Q1/(w m ×C p )；
wherein T2 is the outlet temperature of the circulating water, T1 is the inlet temperature of the circulating water, deltaT is the temperature rise temperature of the circulating water, Q1 is the actual heat load of the first condenser, and w m For circulating water mass flow, C p The specific heat capacity is fixed for the sea water at the pipe side. It should be noted that the circulating water inlet temperature parameter is used for representing the temperature of the circulating water when entering the condenser.
Optionally, in the embodiment of the invention, the condenser can be used for absorbing heat, when the circulating water medium enters the condenser, the circulating water medium with lower temperature and fixed temperature can be adopted, and when the circulating water medium after absorbing heat flows out, the temperature is higher, so that the temperature of the circulating water outlet is difficult to be directly measured.
S240, determining a parameter value of an actual vacuum pressure parameter according to the actual heat load parameter of the first condenser and the actual heat load parameter of the second condenser.
Specifically, the parameter value of the actual vacuum pressure parameter of the condenser can be determined according to the determined actual heat load parameter of the first condenser when the nuclear power station is in the first operation working condition and the determined actual heat load parameter of the second condenser when the nuclear power station is in the second operation working condition.
Optionally, determining the parameter value of the actual vacuum pressure parameter according to the actual heat load parameter of the first condenser and the actual heat load parameter of the second condenser includes: based on a heat balance principle of the nuclear power station, establishing an equivalent relation between actual heat load parameters of the first condenser and actual heat load parameters of the second condenser; and determining the parameter value of the actual vacuum pressure parameter according to the equivalent relation and the fixed conversion relation between the actual vacuum pressure parameter and the saturation temperature parameter.
Specifically, based on a heat balance principle of the nuclear power station, an equivalent relation between a first condenser actual heat load parameter determined when the nuclear power station is in a first operation working condition and a second condenser actual heat load parameter determined when the nuclear power station is in the first operation working condition can be determined, and according to a preset conversion relation between an actual vacuum pressure parameter and a saturation temperature parameter, the saturation temperature parameter is converted into the actual vacuum pressure parameter, and a parameter value of the actual vacuum pressure parameter is solved. It should be noted that, according to the equivalent relationship, the parameter value of the actual thermal load parameter of the first condenser is equal to the parameter value of the actual thermal load parameter of the second condenser, at this time, two unknown parameters of the saturated temperature parameter and the actual vacuum pressure parameter exist in the equivalent relationship, and then according to the fixed conversion relationship between the saturated temperature parameter and the actual vacuum pressure parameter, only one unknown parameter of the actual vacuum pressure parameter exists in the equivalent relationship, so that the parameter value of the actual vacuum pressure parameter can be solved.
S250, substituting the parameter value of the actual vacuum pressure parameter into the first unit output parameter to determine the first unit output value of the nuclear power station.
Specifically, after determining the parameter value of the actual vacuum pressure parameter, the first unit output value of the nuclear power station under the first operation condition may be determined by substituting the parameter value of the actual vacuum pressure parameter into the first unit output parameter.
And S260, under the condition that the nuclear power station is in a second operation working condition, determining a second unit output parameter according to the nuclear island thermal power parameter of the nuclear power station, and determining a third condenser actual thermal load parameter according to the second unit output parameter.
The second unit output parameter can be determined through a condenser vacuum pressure correction curve and can be used for determining a second unit output value.
Specifically, under the condition that the nuclear power station is in the second operation working condition, the output parameter of the second unit can be determined according to the heat power parameter of the nuclear island of the nuclear power station, and the actual heat load parameter of the third condenser can be determined according to the output parameter of the second unit.
Alternatively, the second set output parameter may be expressed by the formula:
E 2 ＝E * ×(1+C o2 /100)/[(1+C o1 /100)×(1+C o3 /100)]；
C o3 ＝0.00144×(P n /34.15) 2 +0.8272×(P n /34.15)-97.12；
wherein E is 2 For the second unit to output, E * Is the standard unit output of the nuclear power station, C o1 C is the vacuum correction coefficient of the first condenser o2 C is the vacuum correction coefficient of the second condenser o3 Correction coefficient for thermal power of nuclear island, P n Is nuclear island thermal power.
Alternatively, the standard unit output of the nuclear power station is a fixed value, and can be adaptively set according to the person skilled in the art.
Optionally, the actual heat load parameter of the third condenser may be represented by the following formula:
wherein Q is 3 Is the actual heat load of the third condenser,for nuclear island thermal power, +.>Is mainly the heat quantity carried by the water supply pump group, delta Q * E is the heat load loss of the condenser 2 And outputting force for the second unit.
Optionally, in the embodiment of the present invention, under the condition that the nuclear power plant is in the second operating condition, the value of the thermal power of the nuclear island is a dynamic change value, the parameter value of the actual vacuum pressure parameter of the condenser is a fixed value (13.3 KPa), and the heat value brought by the main water supply pump set and the heat load loss value of the condenser are fixed values, which can be adaptively set according to those skilled in the art.
S270, based on a heat balance principle of the nuclear power station, establishing an equivalent relation between the actual heat load parameter of the third condenser and the actual heat load parameter of the second condenser.
Specifically, based on the heat balance principle of the nuclear power plant, the equivalent relation between the actual heat load parameter of the third condenser determined under the second operation condition of the nuclear power plant and the actual heat load parameter of the second condenser determined under the second operation condition of the nuclear power plant can be determined, and the parameter value of the heat power of the nuclear island can be solved.
S280, determining a parameter value of the heat power parameter of the nuclear island according to the equivalent relation, substituting the parameter value of the heat power parameter of the nuclear island into the output parameter of the second unit, and determining the output value of the second unit of the nuclear power station.
Specifically, according to the equivalent relationship, the parameter value of the actual heat load parameter of the third condenser is equal to the parameter value of the actual heat load parameter of the second condenser, at this time, an unknown parameter of the heat power of the nuclear island exists in the equivalent relationship, so that the parameter value of the heat power of the nuclear island can be solved, and after the parameter value of the heat power of the nuclear island is determined, the parameter value of the heat power of the nuclear island can be substituted into the output parameter of the second unit, so as to determine the output value of the second unit of the nuclear power station under the second operating condition
S290, determining a change curve of the unit output according to the first unit output value, the second unit output value and the operation condition parameters of the nuclear power station.
According to the technical scheme, based on a heat balance principle, the first unit output value of the nuclear power station under the first operation condition is determined by determining the first condenser actual heat load parameter and the second condenser actual heat load parameter of the nuclear power station under the first operation condition, the second unit output value of the nuclear power station under the second operation condition is determined by determining the third condenser actual heat load parameter and the second condenser actual heat load parameter of the nuclear power station under the second operation condition, the change curve of the unit output of the nuclear power station under the operation of the circulating water pump is determined by the first unit output value and the second unit output value, a basis is provided for analysis of the unit output and economy of the nuclear power station, and the Internet power and the power plant benefit are improved.
Example III
Fig. 3 is a schematic structural diagram of a unit output determining device of a nuclear power station according to a third embodiment of the present invention. As shown in fig. 3, the apparatus includes:
the first operation condition module 310 is configured to determine, when the nuclear power plant is in a first operation condition, an actual heat load parameter of the first condenser according to an actual vacuum pressure parameter of the condenser, and determine an actual heat load parameter of the second condenser according to a saturation temperature parameter of the condenser;
the first unit output module 320 is configured to determine a first unit output value of the nuclear power station according to the first condenser actual thermal load parameter and the second condenser actual thermal load parameter;
the second operation condition module 330 is configured to determine an actual thermal load parameter of the third condenser according to a nuclear island thermal power parameter of the nuclear power plant and determine an actual thermal load parameter of the second condenser when the nuclear power plant is in the second operation condition;
the second unit output module 340 is configured to determine a second unit output value of the nuclear power plant according to the third condenser actual thermal load parameter and the second condenser actual thermal load parameter;
the curve determining module 350 is configured to determine a change curve of the unit output according to the first unit output value, the second unit output value, and the operation condition parameter of the nuclear power station.
According to the technical scheme provided by the embodiment of the invention, the unit output value of the nuclear power station under the first working condition and the second working condition is determined, so that the change curve of the unit output of the nuclear power station under the single circulating water pump is determined, the situation that the unit output of the nuclear power station is not required to be maintained at 40% under the long-term operation of the single circulating water pump is realized, and the unit output of the nuclear power station is dynamically adjusted according to the seawater temperature, so that the unit output of the nuclear power station operates according to the optimal output, and the Internet surfing electric quantity and the power plant benefit are improved.
Optionally, the first operating condition module 310 includes:
the first heat load determining unit is used for determining a first unit output parameter according to the actual vacuum pressure parameter of the condenser and determining the actual heat load parameter of the first condenser according to the first unit output parameter under the condition that the nuclear power station is in a first operation working condition;
the second heat load determining unit is used for determining a logarithmic average temperature difference parameter of the condenser according to the saturated temperature parameter of the condenser and determining an actual heat load parameter of the second condenser according to the logarithmic average temperature difference parameter.
Optionally, the first unit output module 320 includes:
the outlet temperature determining unit is used for determining the circulating water temperature rising parameter of the condenser according to the actual heat load parameter of the first condenser and determining the circulating water outlet temperature parameter of the condenser in the actual heat load parameter of the second condenser according to the circulating water temperature rising parameter;
The vacuum pressure parameter value determining unit is used for determining the parameter value of the actual vacuum pressure parameter according to the actual heat load parameter of the first condenser and the actual heat load parameter of the second condenser;
and the first unit output value determining unit is used for substituting the parameter value of the actual vacuum pressure parameter into the first unit output parameter to determine the first unit output value of the nuclear power station.
Alternatively, the vacuum pressure parameter value determining unit may be specifically configured to: based on a heat balance principle of the nuclear power station, establishing an equivalent relation between actual heat load parameters of the first condenser and actual heat load parameters of the second condenser; and determining the parameter value of the actual vacuum pressure parameter according to the equivalent relation and the fixed conversion relation between the actual vacuum pressure parameter and the saturation temperature parameter.
Optionally, the second operating condition module 330 may be specifically configured to: and under the condition that the nuclear power station is in a second operation working condition, determining a second unit output parameter according to the nuclear island thermal power parameter of the nuclear power station, and determining the actual thermal load parameter of the third condenser according to the second unit output parameter.
Optionally, the second unit output module 340 includes:
the equivalent relation establishing unit is used for establishing an equivalent relation between the actual heat load parameter of the third condenser and the actual heat load parameter of the second condenser based on the heat balance principle of the nuclear power station;
And the second unit output value determining unit is used for determining the parameter value of the nuclear island thermal power parameter according to the equivalent relation, substituting the parameter value of the nuclear island thermal power parameter into the second unit output parameter and determining the second unit output value of the nuclear power station.
Optionally, under the first operation condition, the thermal power of the nuclear island in the nuclear power station can be full power, and the actual vacuum pressure parameter value of the condenser in the nuclear power station is smaller than or equal to the alarm threshold value; the actual vacuum pressure parameter value of the condenser in the nuclear power plant under the second operating condition may be greater than the alarm threshold.
The unit output determining device of the nuclear power station provided by the embodiment of the invention can execute the unit output determining method of the nuclear power station provided by any embodiment of the invention, and has the corresponding functional modules and beneficial effects of the executing method.
Example IV
Fig. 4 shows a schematic diagram of an electronic device 410 that may be used to implement an embodiment of the invention. Electronic devices are intended to represent various forms of digital computers, such as laptops, desktops, workstations, personal digital assistants, servers, blade servers, mainframes, and other appropriate computers. Electronic equipment may also represent various forms of mobile devices, such as personal digital processing, cellular telephones, smartphones, wearable devices (e.g., helmets, glasses, watches, etc.), and other similar computing devices. The components shown herein, their connections and relationships, and their functions, are meant to be exemplary only, and are not meant to limit implementations of the inventions described and/or claimed herein.
As shown in fig. 4, the electronic device 410 includes at least one processor 411, and a memory, such as a Read Only Memory (ROM) 412, a Random Access Memory (RAM) 413, etc., communicatively connected to the at least one processor 411, wherein the memory stores computer programs executable by the at least one processor, and the processor 411 may perform various suitable actions and processes according to the computer programs stored in the Read Only Memory (ROM) 412 or the computer programs loaded from the storage unit 418 into the Random Access Memory (RAM) 413. In the RAM 413, various programs and data required for the operation of the electronic device 410 may also be stored. The processor 411, the ROM 412, and the RAM 413 are connected to each other through a bus 414. An input/output (I/O) interface 415 is also connected to bus 414.
Various components in the electronic device 410 are connected to the I/O interface 415, including: an input unit 416 such as a keyboard, a mouse, etc.; an output unit 417 such as various types of displays, speakers, and the like; a storage unit 418, such as a magnetic disk, optical disk, or the like; and a communication unit 419 such as a network card, modem, wireless communication transceiver, etc. The communication unit 419 allows the electronic device 410 to exchange information/data with other devices through a computer network such as the internet and/or various telecommunication networks.
The processor 411 may be a variety of general and/or special purpose processing components having processing and computing capabilities. Some examples of processor 411 include, but are not limited to, a Central Processing Unit (CPU), a Graphics Processing Unit (GPU), various specialized Artificial Intelligence (AI) computing chips, various processors running machine learning model algorithms, digital Signal Processors (DSPs), and any suitable processor, controller, microcontroller, etc. The processor 411 performs the various methods and processes described above, such as the unit output determination method of a nuclear power plant.
In some embodiments, the plant output determination method of the nuclear power plant may be implemented as a computer program tangibly embodied on a computer-readable storage medium, such as the storage unit 418. In some embodiments, some or all of the computer program may be loaded and/or installed onto the electronic device 410 via the ROM 412 and/or the communication unit 419. When the computer program is loaded into RAM 413 and executed by processor 411, one or more steps of the unit output determination method of a nuclear power plant described above may be performed. Alternatively, in other embodiments, the processor 411 may be configured to perform the unit output determination method of the nuclear power plant in any other suitable manner (e.g., by means of firmware).
Various implementations of the systems and techniques described here above can be implemented in digital electronic circuitry, integrated circuit systems, field Programmable Gate Arrays (FPGAs), application Specific Integrated Circuits (ASICs), application Specific Standard Products (ASSPs), systems On Chip (SOCs), complex Programmable Logic Devices (CPLDs), computer hardware, firmware, software, and/or combinations thereof. These various embodiments may include: implemented in one or more computer programs, the one or more computer programs may be executed and/or interpreted on a programmable system including at least one programmable processor, which may be a special purpose or general-purpose programmable processor, that may receive data and instructions from, and transmit data and instructions to, a storage system, at least one input device, and at least one output device.
A computer program for carrying out methods of the present invention may be written in any combination of one or more programming languages. These computer programs may be provided to a processor of a general purpose computer, special purpose computer, or other programmable data processing apparatus, such that the computer programs, when executed by the processor, cause the functions/acts specified in the flowchart and/or block diagram block or blocks to be implemented. The computer program may execute entirely on the machine, partly on the machine, as a stand-alone software package, partly on the machine and partly on a remote machine or entirely on the remote machine or server.
In the context of the present invention, a computer-readable storage medium may be a tangible medium that can contain, or store a computer program for use by or in connection with an instruction execution system, apparatus, or device. The computer readable storage medium may include, but is not limited to, an electronic, magnetic, optical, electromagnetic, infrared, or semiconductor system, apparatus, or device, or any suitable combination of the foregoing. Alternatively, the computer readable storage medium may be a machine readable signal medium. More specific examples of a machine-readable storage medium would include an electrical connection based on one or more wires, a portable computer diskette, a hard disk, a Random Access Memory (RAM), a read-only memory (ROM), an erasable programmable read-only memory (EPROM or flash memory), an optical fiber, a portable compact disc read-only memory (CD-ROM), an optical storage device, a magnetic storage device, or any suitable combination of the foregoing.
To provide for interaction with a user, the systems and techniques described here can be implemented on an electronic device having: a display device (e.g., a CRT (cathode ray tube) or LCD (liquid crystal display) monitor) for displaying information to a user; and a keyboard and a pointing device (e.g., a mouse or a trackball) through which a user can provide input to the electronic device. Other kinds of devices may also be used to provide for interaction with a user; for example, feedback provided to the user may be any form of sensory feedback (e.g., visual feedback, auditory feedback, or tactile feedback); and input from the user may be received in any form, including acoustic input, speech input, or tactile input.
The systems and techniques described here can be implemented in a computing system that includes a background component (e.g., as a data server), or that includes a middleware component (e.g., an application server), or that includes a front-end component (e.g., a user computer having a graphical user interface or a web browser through which a user can interact with an implementation of the systems and techniques described here), or any combination of such background, middleware, or front-end components. The components of the system can be interconnected by any form or medium of digital data communication (e.g., a communication network). Examples of communication networks include: local Area Networks (LANs), wide Area Networks (WANs), blockchain networks, and the internet.
The computing system may include clients and servers. The client and server are typically remote from each other and typically interact through a communication network. The relationship of client and server arises by virtue of computer programs running on the respective computers and having a client-server relationship to each other. The server can be a cloud server, also called a cloud computing server or a cloud host, and is a host product in a cloud computing service system, so that the defects of high management difficulty and weak service expansibility in the traditional physical hosts and VPS service are overcome.
It should be appreciated that various forms of the flows shown above may be used to reorder, add, or delete steps. For example, the steps described in the present invention may be performed in parallel, sequentially, or in a different order, so long as the desired results of the technical solution of the present invention are achieved, and the present invention is not limited herein.
The above embodiments do not limit the scope of the present invention. It will be apparent to those skilled in the art that various modifications, combinations, sub-combinations and alternatives are possible, depending on design requirements and other factors. Any modifications, equivalent substitutions and improvements made within the spirit and principles of the present invention should be included in the scope of the present invention.
Claims (10)
1. A method for determining unit output of a nuclear power plant, comprising:
under the condition that the nuclear power station is in a first operation condition, determining an actual heat load parameter of a first condenser according to an actual vacuum pressure parameter of the condenser, and determining an actual heat load parameter of a second condenser according to a saturation temperature parameter of the condenser;
determining a first unit output value of the nuclear power station according to the first condenser actual heat load parameter and the second condenser actual heat load parameter;
Under the condition that the nuclear power station is in a second operation condition, determining an actual thermal load parameter of a third condenser according to a nuclear island thermal power parameter of the nuclear power station, and determining the actual thermal load parameter of the second condenser;
determining a second unit output value of the nuclear power station according to the third condenser actual heat load parameter and the second condenser actual heat load parameter;
and determining a change curve of the unit output according to the first unit output value, the second unit output value and the operation condition parameters of the nuclear power station.
2. The method of claim 1, wherein determining the first condenser actual thermal load parameter based on the condenser actual vacuum pressure parameter and determining the second condenser actual thermal load parameter based on the condenser saturation temperature parameter when the nuclear power plant is in the first operating condition comprises:
under the condition that the nuclear power station is in a first operation working condition, determining a first unit output parameter according to an actual vacuum pressure parameter of the condenser, and determining an actual heat load parameter of the first condenser according to the first unit output parameter;
and determining a logarithmic average temperature difference parameter of the condenser according to the saturated temperature parameter of the condenser, and determining an actual heat load parameter of the second condenser according to the logarithmic average temperature difference parameter.
3. The method of claim 1, wherein the determining a first unit output value of the nuclear power plant based on the first condenser actual heat load parameter and the second condenser actual heat load parameter comprises:
determining a circulating water temperature rise parameter of the condenser according to the actual heat load parameter of the first condenser, and determining a circulating water outlet temperature parameter of the condenser in the actual heat load parameter of the second condenser according to the circulating water temperature rise parameter;
determining a parameter value of the actual vacuum pressure parameter according to the actual heat load parameter of the first condenser and the actual heat load parameter of the second condenser;
substituting the parameter value of the actual vacuum pressure parameter into the first unit output parameter to determine the first unit output value of the nuclear power station.
4. A method according to claim 3, wherein said determining a parameter value of said actual vacuum pressure parameter from said first condenser actual heat load parameter and said second condenser actual heat load parameter comprises:
based on a heat balance principle of the nuclear power station, establishing an equivalent relation between the actual heat load parameters of the first condenser and the actual heat load parameters of the second condenser;
And determining the parameter value of the actual vacuum pressure parameter according to the equivalent relation and the fixed conversion relation between the actual vacuum pressure parameter and the saturation temperature parameter.
5. The method of claim 1, wherein determining the third condenser actual thermal load parameter from the nuclear island thermal power parameter of the nuclear power plant when the nuclear power plant is in the second operating condition comprises:
and under the condition that the nuclear power station is in a second operation working condition, determining a second unit output parameter according to the nuclear island thermal power parameter of the nuclear power station, and determining a third condenser actual thermal load parameter according to the second unit output parameter.
6. The method of claim 1, wherein the determining a second unit output value of the nuclear power plant based on the third condenser actual heat load parameter and the second condenser actual heat load parameter comprises:
based on a heat balance principle of the nuclear power station, establishing an equivalent relation between the actual heat load parameter of the third condenser and the actual heat load parameter of the second condenser;
and determining the parameter value of the nuclear island thermal power parameter according to the equivalent relation, substituting the parameter value of the nuclear island thermal power parameter into the second unit output parameter, and determining the second unit output value of the nuclear power station.
7. The method of claim 1, wherein the nuclear island thermal power in the nuclear power plant is full power and the actual vacuum pressure parameter value of the condenser in the nuclear power plant is less than or equal to an alarm threshold under the first operating condition; and the actual vacuum pressure parameter value of the condenser in the nuclear power station under the second operation condition is larger than the alarm threshold value.
8. A unit output determining apparatus of a nuclear power plant, comprising:
the first operation working condition module is used for determining the actual heat load parameter of the first condenser according to the actual vacuum pressure parameter of the condenser and determining the actual heat load parameter of the second condenser according to the saturation temperature parameter of the condenser under the condition that the nuclear power station is in the first operation working condition;
the first unit output module is used for determining a first unit output value of the nuclear power station according to the first condenser actual heat load parameter and the second condenser actual heat load parameter;
the second operation working condition module is used for determining the actual heat load parameter of the third condenser according to the heat power parameter of the nuclear island of the nuclear power station and determining the actual heat load parameter of the second condenser under the condition that the nuclear power station is in the second operation working condition;
The second unit output module is used for determining a second unit output value of the nuclear power station according to the third condenser actual thermal load parameter and the second condenser actual thermal load parameter;
and the curve determining module is used for determining a change curve of the unit output according to the first unit output value, the second unit output value and the operation condition parameters of the nuclear power station.
9. An electronic device, the electronic device comprising:
at least one processor; and
a memory communicatively coupled to the at least one processor; wherein,
the memory stores a computer program executable by the at least one processor to enable the at least one processor to perform the plant contribution determination method of the nuclear power plant of any one of claims 1-7.
10. A computer readable storage medium storing computer instructions for causing a processor to perform the method of determining the plant output of a nuclear power plant as claimed in any one of claims 1 to 7.
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