CN118070514A - Nuclear power determination method and device for nuclear reactor and computer equipment - Google Patents

Nuclear power determination method and device for nuclear reactor and computer equipment Download PDF

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Publication number
CN118070514A
CN118070514A CN202410200511.1A CN202410200511A CN118070514A CN 118070514 A CN118070514 A CN 118070514A CN 202410200511 A CN202410200511 A CN 202410200511A CN 118070514 A CN118070514 A CN 118070514A
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power
nuclear
nuclear reactor
model
initial
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CN202410200511.1A
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彭松
冯晓明
易林
谭世杰
李文
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Daya Bay Nuclear Power Operations and Management Co Ltd
Lingdong Nuclear Power Co Ltd
Guangdong Nuclear Power Joint Venture Co Ltd
Lingao Nuclear Power Co Ltd
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Daya Bay Nuclear Power Operations and Management Co Ltd
Lingdong Nuclear Power Co Ltd
Guangdong Nuclear Power Joint Venture Co Ltd
Lingao Nuclear Power Co Ltd
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Priority to CN202410200511.1A priority Critical patent/CN118070514A/en
Publication of CN118070514A publication Critical patent/CN118070514A/en
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Abstract

The application relates to a nuclear power determination method, a nuclear power determination device and computer equipment for a nuclear reactor. The method comprises the following steps: according to the actual running current of the nuclear reactor and the initial power model of the current wheel, the initial nuclear power of the nuclear reactor is determined, when the initial nuclear power is larger than a nuclear power threshold value, the initial power model of the current wheel is adjusted according to the conversion relation between the corresponding nuclear power and the thermal power of the nuclear reactor, the target power model of the current wheel of the nuclear reactor is obtained, and then the target nuclear power of the nuclear reactor is determined according to the target power model of the current wheel and the actual running current. The method can improve the accuracy of the determination of the nuclear power.

Description

Nuclear power determination method and device for nuclear reactor and computer equipment
Technical Field
The present application relates to the field of nuclear power technology, and in particular, to a method and apparatus for determining nuclear power of a nuclear reactor, and a computer device.
Background
With the continuous development of the nuclear power field, in order to ensure the safe operation of a nuclear reactor, an off-pile detection device is required to detect the nuclear power of the nuclear reactor and convert the nuclear power into thermal power for display.
Currently, nuclear power of a nuclear reactor is generally determined by a fixed nuclear power calculation formula and nuclear reactor operating parameters. However, in a high power operation state of a nuclear reactor, only a fixed nuclear power calculation formula is used to determine the nuclear power of the nuclear reactor, which may reduce the accuracy of the nuclear power determination.
Disclosure of Invention
In view of the foregoing, it is desirable to provide a nuclear power determination method, apparatus, and computer device for a nuclear reactor that can improve the accuracy of nuclear reactor thermal power determination.
In a first aspect, the present application provides a method of nuclear power determination for a nuclear reactor. The method comprises the following steps:
Determining the initial nuclear power of the nuclear reactor according to the actual running current of the nuclear reactor and the initial power model of the current wheel;
when the initial nuclear power is larger than the nuclear power threshold, the initial power model of the present round is adjusted according to the conversion relation between the nuclear power and the thermal power corresponding to the nuclear reactor, and a target power model of the present round of the nuclear reactor is obtained;
and determining the target nuclear power of the nuclear reactor according to the target power model of the current wheel and the actual running current.
In one embodiment, before determining the initial nuclear power of the nuclear reactor based on the actual operating current of the nuclear reactor and the current round initial power model, the method further comprises:
Obtaining a standard operating current of a nuclear reactor when the nuclear reactor operates at rated power; taking the ratio between the standard operation current and the historical operation current as a first regulation parameter; wherein, the history running current refers to the current of the nuclear reactor in the previous round when the nuclear reactor normally runs under rated power; and according to the first adjusting parameters, carrying out parameter adjustment on a previous round of target power model of the nuclear reactor to obtain a current round of initial power model of the nuclear reactor.
In one embodiment, according to a first adjustment parameter, parameter adjustment is performed on a previous round of target power model of the nuclear reactor to obtain a current round of initial power model of the nuclear reactor, including:
And taking the product between the first adjusting parameter and the model parameter of the previous round of target power model of the nuclear reactor as the model parameter of the initial power model of the nuclear reactor.
In one embodiment, the method for adjusting the initial power model of the present round according to the conversion relation between the nuclear power and the thermal power corresponding to the nuclear reactor to obtain the target power model of the present round of the nuclear reactor includes:
Determining a second adjustment parameter according to a conversion relation between nuclear power and thermal power corresponding to the nuclear reactor; and adjusting model parameters of the initial power model of the current round by adopting the second adjusting parameters to obtain the target power model of the current round of the nuclear reactor.
In one embodiment, the transformation relationship is characterized by a unitary quadratic function; the adjustment coefficients are determined from the function coefficients of the unitary quadratic function.
In one embodiment, the method further comprises:
When the initial nuclear power is less than or equal to the nuclear power threshold, the initial nuclear power is taken as the target nuclear power of the nuclear reactor.
In a second aspect, the present application also provides a nuclear power determination apparatus for a nuclear reactor. The device comprises:
The initial power determining module is used for determining the initial nuclear power of the nuclear reactor according to the actual running current of the nuclear reactor and the initial power model of the current wheel;
The model determining module is used for adjusting the initial power model of the current round according to the conversion relation between the nuclear power and the thermal power corresponding to the nuclear reactor when the initial nuclear power is larger than the nuclear power threshold value, so as to obtain the target power model of the current round of the nuclear reactor;
And the target power determining module is used for determining the target nuclear power of the nuclear reactor according to the current wheel target power model and the actual running current.
In a third aspect, the present application also provides a computer device. The computer device comprises a memory storing a computer program and a processor which when executing the computer program performs the steps of:
Determining the initial nuclear power of the nuclear reactor according to the actual running current of the nuclear reactor and the initial power model of the current wheel;
when the initial nuclear power is larger than the nuclear power threshold, the initial power model of the present round is adjusted according to the conversion relation between the nuclear power and the thermal power corresponding to the nuclear reactor, and a target power model of the present round of the nuclear reactor is obtained;
and determining the target nuclear power of the nuclear reactor according to the target power model of the current wheel and the actual running current.
In a fourth aspect, the present application also provides a computer-readable storage medium. The computer readable storage medium having stored thereon a computer program which when executed by a processor performs the steps of:
Determining the initial nuclear power of the nuclear reactor according to the actual running current of the nuclear reactor and the initial power model of the current wheel;
when the initial nuclear power is larger than the nuclear power threshold, the initial power model of the present round is adjusted according to the conversion relation between the nuclear power and the thermal power corresponding to the nuclear reactor, and a target power model of the present round of the nuclear reactor is obtained;
and determining the target nuclear power of the nuclear reactor according to the target power model of the current wheel and the actual running current.
In a fifth aspect, the present application also provides a computer program product. The computer program product comprises a computer program which, when executed by a processor, implements the steps of:
Determining the initial nuclear power of the nuclear reactor according to the actual running current of the nuclear reactor and the initial power model of the current wheel;
when the initial nuclear power is larger than the nuclear power threshold, the initial power model of the present round is adjusted according to the conversion relation between the nuclear power and the thermal power corresponding to the nuclear reactor, and a target power model of the present round of the nuclear reactor is obtained;
and determining the target nuclear power of the nuclear reactor according to the target power model of the current wheel and the actual running current.
According to the nuclear power determining method, the device and the computer equipment of the nuclear reactor, the initial nuclear power of the nuclear reactor is determined according to the actual running current of the nuclear reactor and the initial power model of the current wheel, and under the condition that the initial nuclear power is larger than a nuclear power threshold value, the initial power model of the current wheel is adjusted according to the conversion relation between the corresponding nuclear power and the thermal power of the nuclear reactor, so that the target nuclear power of the nuclear reactor is determined according to the target power model of the current wheel and the actual running current. Compared with the prior art, the nuclear power of the nuclear reactor is determined by adopting a fixed nuclear power calculation formula, the method is adopted, and under the condition that the initial nuclear power is larger than the nuclear power threshold value, the initial power model of the current round is adjusted based on the conversion relation, so that the target power model of the current round is more accurate, the accuracy of the target nuclear power of the nuclear reactor is improved, and the stable operation of the nuclear reactor is further ensured.
Drawings
FIG. 1A is a graph showing the trend of the change of nuclear power and thermal power in the prior art;
FIG. 1B is a flow diagram of a method of nuclear power determination for a nuclear reactor in one embodiment;
FIG. 2 is a flow chart of determining an initial power model of a present round in one embodiment;
FIG. 3 is a flow chart of determining a target power model for a present round in one embodiment;
FIG. 4 is a flow chart of a method of determining nuclear power of a nuclear reactor in another embodiment;
FIG. 5 is a block diagram of a nuclear power determination apparatus of a nuclear reactor in one embodiment;
FIG. 6 is a block diagram of a nuclear power determination apparatus of a nuclear reactor in another embodiment;
FIG. 7 is a block diagram of a nuclear power determination apparatus of a nuclear reactor in yet another embodiment;
Fig. 8 is an internal structural diagram of a computer device in one embodiment.
Detailed Description
The present application will be described in further detail with reference to the drawings and examples, in order to make the objects, technical solutions and advantages of the present application more apparent. It should be understood that the specific embodiments described herein are for purposes of illustration only and are not intended to limit the scope of the application.
With the continuous development of the nuclear power field, in order to ensure the safe operation of a nuclear reactor, an off-pile detection device is required to detect the nuclear power of the nuclear reactor and convert the nuclear power into thermal power for display.
Currently, nuclear power of a nuclear reactor is generally determined by a fixed nuclear power calculation formula and nuclear reactor operating parameters. However, in a high power operating state of the nuclear reactor (e.g., the nuclear power and the thermal power are greater than the first power, which is typically 30% of the rated power), it is understood that the first power may be adaptively adjusted according to the configuration of the nuclear reactor, where the rated power refers to the maximum power that the nuclear reactor can operate at, and is used to monitor whether the nuclear reactor is overloaded. Referring to fig. 1A, in which the horizontal axis is the thermal power PTH, the vertical axis is the nuclear power PR, and the RPN is the off-pile detection device, it is known from the coordinate point (1,1.26) that when the thermal power reaches the rated power, the nuclear power has reached 126% of the rated power, that is, the nuclear power needs to reach 126% of the rated power to be converted into the thermal power equal to the rated power. At this time, since there is a large deviation between the thermal power and the nuclear power, the reactor is likely to jump directly, and thus it is known that the nuclear power and the thermal power have a large difference in the high-power operation state of the nuclear reactor, and the safety of the nuclear power operation is reduced.
Based on this, in one embodiment, as shown in fig. 1B, there is provided a nuclear power determining method of a nuclear reactor, which is exemplified as an application of the method to an off-stack detection apparatus, including the steps of:
s101, determining the initial nuclear power of the nuclear reactor according to the actual running current of the nuclear reactor and the initial power model of the current wheel.
Wherein the actual operating current refers to the current in the reactor when the reactor is operating, and may include an upper operating current and a lower operating current; the initial power model of the round refers to a trained model, which can be but is not limited to a decision tree model, a random forest model, a support vector machine model, a neural network model, a model degree lifting decision tree model and the like, and is used for determining the nuclear power of the reactor during the running in the round according to the actual running current; the initial core power refers to the core power output by the initial power model of the present round.
Alternatively, the off-stack detection device may directly obtain the actual operating current of the nuclear reactor through a measurement channel connected to the nuclear reactor; and then, the actual running current is directly input into a trained primary initial power model, and the primary initial power model determines the initial nuclear power of the nuclear reactor according to the actual running current and model parameters.
And S102, when the initial nuclear power is larger than the nuclear power threshold, adjusting the initial power model of the present round according to the conversion relation between the nuclear power and the thermal power corresponding to the nuclear reactor, and obtaining the target power model of the present round of the nuclear reactor.
The core power threshold is a numerical value for measuring whether the initial core power can be directly used as the target core power; the round of target power model refers to a neural network model obtained after the round of initial power model is adjusted.
It is understood that the nuclear power of the nuclear reactor core varies greatly in the power up phase. Therefore, in order to ensure the accuracy of the determination of the nuclear power, the initial power model of the present round needs to be adjusted according to the conversion relationship between the nuclear power and the thermal power corresponding to the nuclear reactor, so that the nuclear power output by the target power model of the present round after adjustment is more accurate.
Optionally, in order to more accurately measure whether the nuclear reactor is in a high power stage, the nuclear power threshold may be determined according to a corresponding curve of nuclear power and thermal power of the nuclear reactor in a historical turn. For example, 30% of rated power may be used as the core power threshold.
Further, the initial nuclear power and the nuclear power threshold value can be compared, and under the condition that the initial nuclear power is larger than the nuclear power threshold value, the initial power model of the present round can be trained based on the conversion relation between the nuclear power and the thermal power corresponding to the nuclear reactor, so that the target power model of the present round of the nuclear reactor is obtained.
Accordingly, in the case where the initial nuclear power is less than or equal to the nuclear power threshold, the initial nuclear power is taken as a target nuclear power of the nuclear reactor.
It will be appreciated that since the change in power distribution is small in the low power phase of the nuclear reactor, the initial nuclear power may be directly taken as the target nuclear power of the nuclear reactor.
S103, determining the target nuclear power of the nuclear reactor according to the current round target power model and the actual running current.
Alternatively, after the current round target power model is determined, the actual operating current may be directly input into the current round target power model to determine the target nuclear power of the nuclear reactor.
According to the nuclear power determining method of the nuclear reactor, the initial nuclear power of the nuclear reactor is determined according to the actual running current of the nuclear reactor and the initial power model of the current wheel, and under the condition that the initial nuclear power is larger than a nuclear power threshold value, the initial power model of the current wheel is adjusted according to the conversion relation between the corresponding nuclear power and the thermal power of the nuclear reactor to obtain the target power model of the current wheel of the nuclear reactor, and then the target nuclear power of the nuclear reactor is determined according to the target power model of the current wheel and the actual running current. Compared with the prior art, the nuclear power of the nuclear reactor is determined by adopting a fixed nuclear power calculation formula, the method is adopted, and under the condition that the initial nuclear power is larger than the nuclear power threshold value, the initial power model of the current round is adjusted based on the conversion relation, so that the target power model of the current round is more accurate, the accuracy of the target nuclear power of the nuclear reactor is improved, and the stable operation of the nuclear reactor is further ensured.
In order to ensure the accuracy of the initial power model of the present round, before determining the initial nuclear power of the nuclear reactor, in this embodiment, an alternative manner of determining the initial power model of the present round is provided, as shown in fig. 2, and specifically includes the following steps:
s201, obtaining standard operation current of the nuclear reactor when the nuclear reactor operates at rated power.
The standard operating current refers to the current of the nuclear reactor in normal operation under rated power.
It will be appreciated that in order to ensure the accuracy of the standard operating current, the average value of the theoretical operating currents of the components of the nuclear reactor when operating at rated power may be taken as the standard operating current.
S202, taking the ratio between the standard operation current and the historical operation current as a first adjustment parameter.
Wherein, the historical operating current refers to the current of the nuclear reactor in the previous round when the nuclear reactor normally operates under rated power; the first tuning parameter refers to a proportional value for tuning the model parameters.
Optionally, after determining the standard operating current, the historical operating current of the previous round of operation of the nuclear reactor at the rated power may be divided by the standard operating current, and the first adjustment parameter may be calculated.
And S203, carrying out parameter adjustment on a previous round of target power model of the nuclear reactor according to the first adjustment parameters to obtain a current round of initial power model of the nuclear reactor.
Optionally, after determining the first adjustment parameter, parameters in a previous round of target power model of the nuclear reactor may be adjusted based on the first adjustment parameter to obtain a current round of initial power model of the nuclear reactor. For example, the product between the first tuning parameter and the model parameter of the previous round of the target power model of the nuclear reactor may be taken as the model parameter of the current round of the initial power model of the nuclear reactor.
Alternatively, the product between the first tuning parameter and the model parameter of the previous round of the target power model of the nuclear reactor may be referred to as the model parameter of the current round of the initial power model of the nuclear reactor by referring to the following equations (1) and (2). Wherein, K U refers to the upper matching coefficient between the nuclear reactor operating current and the nuclear reactor nuclear power in the power model, and K L refers to the lower matching coefficient between the nuclear reactor operating current and the nuclear reactor nuclear power in the power model; k U (n+1) and K L (n+1) refer to model parameters of the initial power model of the present round (n+1 round); k U (n) and K L (n) refer to model parameters of the last round (nth round) of the target power model; i n refers to the historical operating current, I n+1 refers to the standard operating current, and further, I n/In+1 refers to the first tuning parameter.
(1)
(2)
In this embodiment, parameter adjustment is performed on a previous round of target power model of the nuclear reactor according to the first adjustment parameter to obtain a current round of initial power model of the nuclear reactor, so that accuracy of the current round of initial power model can be ensured.
In order to ensure the accuracy of the target power model of the present wheel, in this embodiment, an alternative way of determining the target power model of the present wheel is provided, as shown in fig. 3, and specifically includes the following steps:
s301, determining a second adjusting parameter according to the conversion relation between the nuclear power and the thermal power corresponding to the nuclear reactor.
The conversion relation is represented by a unitary quadratic function; the adjustment coefficients are determined from the function coefficients of the unitary quadratic function.
Alternatively, since the conversion relationship can be characterized by a unitary quadratic function, i.e., the conversion relationship can be assumed to beWherein a and b are the function coefficients of a unitary quadratic function; x represents thermal power; y represents the target core power; therefore, the second tuning parameter m needs to be met/>
Further, when the nuclear reactor is operated at rated power, both the nuclear power and the thermal power are 1 in the conversion relationship, i.eConversion can obtain/>
S302, adjusting model parameters of the initial power model of the current round by adopting second adjusting parameters to obtain the target power model of the current round of the nuclear reactor.
Alternatively, the model parameters of the current round target power model may be determined according to the second adjustment parameters and the model parameters of the current round initial power model with reference to the following equations (3) and (4). Wherein, K U '(n+1) and K L' (n+1) refer to model parameters of the current round of target power model.
(3)
(4)
Further, the current round target power model of the nuclear reactor can be determined according to model parameters of the current round target power model.
In this embodiment, the second adjustment parameter is adopted to adjust the model parameter of the primary power model to obtain the primary target power model of the nuclear reactor, so that the accuracy of the primary target power model can be ensured.
Fig. 4 is a flow chart of a method for determining nuclear power of a nuclear reactor according to another embodiment, and on the basis of the above embodiment, this embodiment provides an alternative example of the method for determining nuclear power of a nuclear reactor. With reference to fig. 4, the specific implementation procedure is as follows:
S401, obtaining standard operation current of the nuclear reactor when the nuclear reactor operates under rated power.
S402, taking the ratio between the standard operation current and the historical operation current as a first adjustment parameter.
The historical operating current refers to the current of the nuclear reactor in the previous round when the nuclear reactor normally operates at rated power.
S403, taking the product between the first adjustment parameter and the model parameter of the previous round of target power model of the nuclear reactor as the model parameter of the initial power model of the nuclear reactor.
S404, determining the initial nuclear power of the nuclear reactor according to the actual running current of the nuclear reactor and the initial power model of the current round.
S405, judging whether the initial core power is larger than a core power threshold, if so, executing S406; if not, S409 is performed.
S406, determining a second adjusting parameter according to the conversion relation between the nuclear power and the thermal power corresponding to the nuclear reactor.
S407, adjusting the model parameters of the initial power model of the current round by adopting the second adjusting parameters to obtain the target power model of the current round of the nuclear reactor.
The conversion relation is represented by a unitary quadratic function; the adjustment coefficients are determined from the function coefficients of the unitary quadratic function.
S408, determining the target nuclear power of the nuclear reactor according to the current round target power model and the actual running current.
S409, taking the initial nuclear power as the target nuclear power of the nuclear reactor.
The specific process of S401 to S409 may refer to the description of the foregoing method embodiment, and its implementation principle and technical effect are similar, and are not repeated herein.
It should be understood that, although the steps in the flowcharts related to the embodiments described above are sequentially shown as indicated by arrows, these steps are not necessarily sequentially performed in the order indicated by the arrows. The steps are not strictly limited to the order of execution unless explicitly recited herein, and the steps may be executed in other orders. Moreover, at least some of the steps in the flowcharts described in the above embodiments may include a plurality of steps or a plurality of stages, which are not necessarily performed at the same time, but may be performed at different times, and the order of the steps or stages is not necessarily performed sequentially, but may be performed alternately or alternately with at least some of the other steps or stages.
Based on the same inventive concept, the embodiment of the application also provides a nuclear power determining device of the nuclear reactor for realizing the nuclear power determining method of the nuclear reactor. The implementation of the solution provided by the device is similar to the implementation described in the above method, so the specific limitations in the embodiments of the nuclear power determining device for one or more nuclear reactors provided below may be referred to the above limitations of the nuclear power determining method for a nuclear reactor, and will not be repeated here.
In one embodiment, as shown in fig. 5, there is provided a nuclear power determining apparatus 1 of a nuclear reactor, comprising: an initial power determination module 10, a model determination module 20, and a target power determination module 30, wherein:
An initial power determining module 10 for determining an initial nuclear power of the nuclear reactor according to an actual operating current of the nuclear reactor and the initial power model of the present round;
the model determining module 20 is configured to adjust the initial power model of the present round according to a conversion relationship between the nuclear power and the thermal power corresponding to the nuclear reactor, to obtain a target power model of the present round of the nuclear reactor, when the initial nuclear power is greater than the nuclear power threshold;
The target power determination module 30 is configured to determine a target nuclear power of the nuclear reactor according to the current round target power model and the actual operating current.
In one embodiment, the nuclear power determining apparatus 1 of the nuclear reactor further includes a model adjustment module 40 before determining the initial nuclear power of the nuclear reactor according to the actual operating current of the nuclear reactor and the current initial power model of the present round, wherein the model adjustment module 40 includes:
A current acquisition unit 41 for acquiring a standard operating current when the nuclear reactor is operated at a rated power;
A ratio determining unit 42 for taking as a first adjustment parameter a ratio between a standard operating current and a historical operating current of a previous round of operation of the nuclear reactor at a rated power;
The model adjustment unit 43 is configured to perform parameter adjustment on a previous round of target power model of the nuclear reactor according to the first adjustment parameter, so as to obtain a current round of initial power model of the nuclear reactor.
In one embodiment, the model adjustment unit 43 is specifically configured to:
And taking the product between the first adjusting parameter and the model parameter of the previous round of target power model of the nuclear reactor as the model parameter of the initial power model of the nuclear reactor.
In one embodiment, as shown in FIG. 7, the model determination module 20 includes:
a parameter determining unit 21, configured to determine a second adjustment parameter according to a conversion relationship between the nuclear power and the thermal power corresponding to the nuclear reactor;
The model determining unit 22 is configured to adjust the model parameters of the primary initial power model by using the second adjustment parameters, so as to obtain the primary target power model of the nuclear reactor.
In one embodiment, the transformation relationship is characterized by a unitary quadratic function; the adjustment coefficients are determined from the function coefficients of the unitary quadratic function.
In one embodiment, the target power determination module 30 is further configured to:
in the event that the initial nuclear power is less than or equal to the nuclear power threshold, the initial nuclear power is taken as the target nuclear power for the nuclear reactor.
The respective modules in the nuclear power determining apparatus of the nuclear reactor described above may be implemented in whole or in part by software, hardware, and a combination thereof. The above modules may be embedded in hardware or may be independent of a processor in the computer device, or may be stored in software in a memory in the computer device, so that the processor may call and execute operations corresponding to the above modules.
In one embodiment, a computer device is provided, which may be a server, and the internal structure of which may be as shown in fig. 8. The computer device includes a processor, a memory, an Input/Output interface (I/O) and a communication interface. The processor, the memory and the input/output interface are connected through a system bus, and the communication interface is connected to the system bus through the input/output interface. Wherein the processor of the computer device is configured to provide computing and control capabilities. The memory of the computer device includes a non-volatile storage medium and an internal memory. The non-volatile storage medium stores an operating system, computer programs, and a database. The internal memory provides an environment for the operation of the operating system and computer programs in the non-volatile storage media. The database of the computer device is used for storing data such as the operating current of the nuclear reactor. The input/output interface of the computer device is used to exchange information between the processor and the external device. The communication interface of the computer device is used for communicating with an external terminal through a network connection. The computer program, when executed by a processor, implements a method of nuclear power determination for a nuclear reactor.
It will be appreciated by those skilled in the art that the structure shown in FIG. 8 is merely a block diagram of some of the structures associated with the present inventive arrangements and is not limiting of the computer device to which the present inventive arrangements may be applied, and that a particular computer device may include more or fewer components than shown, or may combine some of the components, or have a different arrangement of components.
In one embodiment, a computer device is provided comprising a memory and a processor, the memory having stored therein a computer program, the processor when executing the computer program performing the steps of:
Determining the initial nuclear power of the nuclear reactor according to the actual running current of the nuclear reactor and the initial power model of the current wheel;
under the condition that the initial nuclear power is larger than a nuclear power threshold value, the initial power model of the current round is adjusted according to the conversion relation between the nuclear power and the thermal power corresponding to the nuclear reactor, and a target power model of the current round of the nuclear reactor is obtained;
and determining the target nuclear power of the nuclear reactor according to the target power model of the current wheel and the actual running current.
In one embodiment, the following steps are embodied when logic in a computer program is executed by a processor prior to determining an initial nuclear power of a nuclear reactor based on an actual operating current of the nuclear reactor and a current initial power model of the current round:
Obtaining a standard operating current of a nuclear reactor when the nuclear reactor operates at rated power; taking the ratio between the standard operation current and the historical operation current of the previous round of operation of the nuclear reactor under the rated power as a first adjustment parameter; and according to the first adjusting parameters, carrying out parameter adjustment on a previous round of target power model of the nuclear reactor to obtain a current round of initial power model of the nuclear reactor.
In one embodiment, when the processor executes logic in the computer program to perform parameter adjustment on a previous round of target power model of the nuclear reactor according to the first adjustment parameter to obtain a current round of initial power model of the nuclear reactor, the following steps are specifically implemented:
And taking the product between the first adjusting parameter and the model parameter of the previous round of target power model of the nuclear reactor as the model parameter of the initial power model of the nuclear reactor.
In one embodiment, when the processor executes logic in the computer program to adjust the initial power model of the present round according to the conversion relationship between the nuclear power and the thermal power corresponding to the nuclear reactor to obtain the target power model of the present round of the nuclear reactor, the following steps are specifically implemented:
Determining a second adjustment parameter according to a conversion relation between nuclear power and thermal power corresponding to the nuclear reactor; and adjusting model parameters of the initial power model of the current round by adopting the second adjusting parameters to obtain the target power model of the current round of the nuclear reactor.
In one embodiment, the transformation relationship is characterized by a unitary quadratic function; the adjustment coefficients are determined from the function coefficients of the unitary quadratic function.
In one embodiment, the following steps are embodied when the processor executes logic in a computer program:
in the event that the initial nuclear power is less than or equal to the nuclear power threshold, the initial nuclear power is taken as the target nuclear power for the nuclear reactor.
In one embodiment, a computer readable storage medium is provided having a computer program stored thereon, which when executed by a processor, performs the steps of:
Determining the initial nuclear power of the nuclear reactor according to the actual running current of the nuclear reactor and the initial power model of the current wheel;
under the condition that the initial nuclear power is larger than a nuclear power threshold value, the initial power model of the current round is adjusted according to the conversion relation between the nuclear power and the thermal power corresponding to the nuclear reactor, and a target power model of the current round of the nuclear reactor is obtained;
and determining the target nuclear power of the nuclear reactor according to the target power model of the current wheel and the actual running current.
In one embodiment, the code logic in the computer program, when executed by the processor, performs the steps of:
Obtaining a standard operating current of a nuclear reactor when the nuclear reactor operates at rated power; taking the ratio between the standard operation current and the historical operation current of the previous round of operation of the nuclear reactor under the rated power as a first adjustment parameter; and according to the first adjusting parameters, carrying out parameter adjustment on a previous round of target power model of the nuclear reactor to obtain a current round of initial power model of the nuclear reactor.
In one embodiment, the code logic for performing parameter adjustment on a previous round of target power model of the nuclear reactor according to the first adjustment parameter in the computer program to obtain the current round of initial power model of the nuclear reactor is executed by the processor, and specifically implements the following steps:
And taking the product between the first adjusting parameter and the model parameter of the previous round of target power model of the nuclear reactor as the model parameter of the initial power model of the nuclear reactor.
In one embodiment, the code logic for adjusting the initial power model of the present round according to the conversion relationship between the nuclear power and the thermal power corresponding to the nuclear reactor in the computer program to obtain the target power model of the present round of the nuclear reactor is executed by the processor, and specifically implements the following steps:
Determining a second adjustment parameter according to a conversion relation between nuclear power and thermal power corresponding to the nuclear reactor; and adjusting model parameters of the initial power model of the current round by adopting the second adjusting parameters to obtain the target power model of the current round of the nuclear reactor.
In one embodiment, the transformation relationship is characterized by a unitary quadratic function; the adjustment coefficients are determined from the function coefficients of the unitary quadratic function.
In one embodiment, the code logic in the computer program, when executed by the processor, performs the steps of:
in the event that the initial nuclear power is less than or equal to the nuclear power threshold, the initial nuclear power is taken as the target nuclear power for the nuclear reactor.
In one embodiment, a computer program product is provided comprising a computer program which, when executed by a processor, performs the steps of:
Determining the initial nuclear power of the nuclear reactor according to the actual running current of the nuclear reactor and the initial power model of the current wheel;
under the condition that the initial nuclear power is larger than a nuclear power threshold value, the initial power model of the current round is adjusted according to the conversion relation between the nuclear power and the thermal power corresponding to the nuclear reactor, and a target power model of the current round of the nuclear reactor is obtained;
And determining the thermal power of the nuclear reactor according to the conversion relation, the current round target power model and the actual running current.
In one embodiment, the computer program, when executed by the processor, performs the steps of:
Obtaining a standard operating current of a nuclear reactor when the nuclear reactor operates at rated power; taking the ratio between the standard operation current and the historical operation current of the previous round of operation of the nuclear reactor under the rated power as a first adjustment parameter; and according to the first adjusting parameters, carrying out parameter adjustment on a previous round of target power model of the nuclear reactor to obtain a current round of initial power model of the nuclear reactor.
In one embodiment, when the computer program is executed by the processor to perform parameter adjustment on a previous round of target power model of the nuclear reactor according to the first adjustment parameter to obtain the operation of the current round of initial power model of the nuclear reactor, the following steps are specifically implemented:
And taking the product between the first adjusting parameter and the model parameter of the previous round of target power model of the nuclear reactor as the model parameter of the initial power model of the nuclear reactor.
In one embodiment, the computer program is executed by the processor to adjust the initial power model of the present round according to the conversion relationship between the nuclear power and the thermal power corresponding to the nuclear reactor, and when obtaining the operation of the target power model of the present round of the nuclear reactor, the following steps are specifically implemented:
Determining a second adjustment parameter according to a conversion relation between nuclear power and thermal power corresponding to the nuclear reactor; and adjusting model parameters of the initial power model of the current round by adopting the second adjusting parameters to obtain the target power model of the current round of the nuclear reactor.
In one embodiment, the transformation relationship is characterized by a unitary quadratic function; the adjustment coefficients are determined from the function coefficients of the unitary quadratic function.
In one embodiment, the computer program, when executed by a processor, performs the steps of:
in the event that the initial nuclear power is less than or equal to the nuclear power threshold, the initial nuclear power is taken as the target nuclear power for the nuclear reactor.
It should be noted that, the data related to the present application (including, but not limited to, the running current of the nuclear reactor, etc.) are all data authorized by the user or sufficiently authorized by each party, and the collection, use and processing of the related data are required to meet the related regulations.
Those skilled in the art will appreciate that implementing all or part of the above described methods may be accomplished by way of a computer program stored on a non-transitory computer readable storage medium, which when executed, may comprise the steps of the embodiments of the methods described above. Any reference to memory, database, or other medium used in embodiments provided herein may include at least one of non-volatile and volatile memory. The nonvolatile Memory may include Read-Only Memory (ROM), magnetic tape, floppy disk, flash Memory, optical Memory, high density embedded nonvolatile Memory, resistive random access Memory (ReRAM), magneto-resistive random access Memory (Magnetoresistive Random Access Memory, MRAM), ferroelectric Memory (Ferroelectric Random Access Memory, FRAM), phase change Memory (PHASE CHANGE Memory, PCM), graphene Memory, and the like. Volatile memory can include random access memory (Random Access Memory, RAM) or external cache memory, and the like. By way of illustration, and not limitation, RAM can be in various forms such as static random access memory (Static Random Access Memory, SRAM) or dynamic random access memory (Dynamic Random Access Memory, DRAM), etc. The databases referred to in the embodiments provided herein may include at least one of a relational database and a non-relational database. The non-relational database may include, but is not limited to, a blockchain-based distributed database, and the like. The processor referred to in the embodiments provided in the present application may be a general-purpose processor, a central processing unit, a graphics processor, a digital signal processor, a programmable logic unit, a data processing logic unit based on quantum computing, or the like, but is not limited thereto.
The technical features of the above embodiments may be arbitrarily combined, and all possible combinations of the technical features in the above embodiments are not described for brevity of description, however, as long as there is no contradiction between the combinations of the technical features, they should be considered as the scope of the description.
The foregoing examples illustrate only a few embodiments of the application and are described in detail herein without thereby limiting the scope of the application. It should be noted that it will be apparent to those skilled in the art that several variations and modifications can be made without departing from the spirit of the application, which are all within the scope of the application. Accordingly, the scope of the application should be assessed as that of the appended claims.

Claims (10)

1. A method of determining nuclear power of a nuclear reactor, the method comprising:
determining initial nuclear power of the nuclear reactor according to actual running current of the nuclear reactor and a primary initial power model;
When the initial nuclear power is larger than a nuclear power threshold, the primary initial power model is adjusted according to a conversion relation between the nuclear power and the thermal power corresponding to the nuclear reactor, and a primary target power model of the nuclear reactor is obtained;
And determining the target nuclear power of the nuclear reactor according to the current round target power model and the actual running current.
2. The method of claim 1, wherein prior to said determining an initial nuclear power of the nuclear reactor based on actual operating current of the nuclear reactor and the current initial power model, the method further comprises:
obtaining a standard operating current of the nuclear reactor when the nuclear reactor operates at rated power;
Taking the ratio of the standard operation current to the historical operation current as a first regulation parameter; wherein, the history running current refers to the current of the nuclear reactor in the previous round when the nuclear reactor normally runs under rated power;
And according to the first adjusting parameters, carrying out parameter adjustment on a previous round of target power model of the nuclear reactor to obtain a current round of initial power model of the nuclear reactor.
3. The method of claim 2, wherein the performing parameter adjustment on the previous round of target power model of the nuclear reactor according to the first adjustment parameter to obtain the current round of initial power model of the nuclear reactor comprises:
and taking the product between the first regulation parameter and the model parameter of the previous round of target power model of the nuclear reactor as the model parameter of the initial power model of the nuclear reactor.
4. The method of claim 1, wherein the adjusting the primary power model according to the conversion relationship between the nuclear power and the thermal power corresponding to the nuclear reactor to obtain the primary target power model of the nuclear reactor comprises:
determining a second adjustment parameter according to a conversion relation between nuclear power and thermal power corresponding to the nuclear reactor;
And adjusting the model parameters of the primary initial power model by adopting the second adjusting parameters to obtain the primary target power model of the nuclear reactor.
5. The method of claim 4, wherein the transformation relationship is characterized by a unitary quadratic function; the adjustment coefficient is determined according to the function coefficient of the unitary quadratic function.
6. The method according to claim 1, wherein the method further comprises:
and when the initial nuclear power is smaller than or equal to the nuclear power threshold value, taking the initial nuclear power as a target nuclear power of the nuclear reactor.
7. A nuclear power determining apparatus of a nuclear reactor, the apparatus comprising:
the initial power determining module is used for determining the initial nuclear power of the nuclear reactor according to the actual running current of the nuclear reactor and the initial power model of the current wheel;
The model determining module is used for adjusting the primary initial power model according to the conversion relation between the nuclear power and the thermal power corresponding to the nuclear reactor when the initial nuclear power is larger than a nuclear power threshold value, so as to obtain a primary target power model of the nuclear reactor;
And the target power determining module is used for determining the target nuclear power of the nuclear reactor according to the current wheel target power model and the actual running current.
8. A computer device comprising a memory and a processor, the memory storing a computer program, characterized in that the processor implements the steps of the method of any of claims 1 to 6 when the computer program is executed.
9. A computer readable storage medium, on which a computer program is stored, characterized in that the computer program, when being executed by a processor, implements the steps of the method of any of claims 1 to 6.
10. A computer program product comprising a computer program, characterized in that the computer program, when being executed by a processor, implements the steps of the method of any of claims 1 to 6.
CN202410200511.1A 2024-02-23 2024-02-23 Nuclear power determination method and device for nuclear reactor and computer equipment Pending CN118070514A (en)

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CN202410200511.1A CN118070514A (en) 2024-02-23 2024-02-23 Nuclear power determination method and device for nuclear reactor and computer equipment

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CN202410200511.1A CN118070514A (en) 2024-02-23 2024-02-23 Nuclear power determination method and device for nuclear reactor and computer equipment

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