CN117936138A - Nuclear power measured value correction method, device, computer equipment and storage medium - Google Patents
Nuclear power measured value correction method, device, computer equipment and storage medium Download PDFInfo
- Publication number
- CN117936138A CN117936138A CN202410049075.2A CN202410049075A CN117936138A CN 117936138 A CN117936138 A CN 117936138A CN 202410049075 A CN202410049075 A CN 202410049075A CN 117936138 A CN117936138 A CN 117936138A
- Authority
- CN
- China
- Prior art keywords
- power measurement
- value
- nuclear
- core
- measured value
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Pending
Links
- 238000012937 correction Methods 0.000 title claims abstract description 160
- 238000000034 method Methods 0.000 title claims abstract description 64
- 238000005259 measurement Methods 0.000 claims abstract description 227
- 238000004590 computer program Methods 0.000 claims abstract description 26
- 230000008569 process Effects 0.000 description 13
- 230000008859 change Effects 0.000 description 8
- 238000010586 diagram Methods 0.000 description 5
- 238000004364 calculation method Methods 0.000 description 4
- 238000012545 processing Methods 0.000 description 4
- 238000004891 communication Methods 0.000 description 3
- 239000003758 nuclear fuel Substances 0.000 description 3
- 230000010355 oscillation Effects 0.000 description 3
- 229910052724 xenon Inorganic materials 0.000 description 3
- FHNFHKCVQCLJFQ-UHFFFAOYSA-N xenon atom Chemical compound [Xe] FHNFHKCVQCLJFQ-UHFFFAOYSA-N 0.000 description 3
- 238000004458 analytical method Methods 0.000 description 2
- 238000013500 data storage Methods 0.000 description 2
- 238000001514 detection method Methods 0.000 description 2
- 230000000694 effects Effects 0.000 description 2
- 238000012986 modification Methods 0.000 description 2
- 230000004048 modification Effects 0.000 description 2
- 230000003068 static effect Effects 0.000 description 2
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 description 1
- 230000032683 aging Effects 0.000 description 1
- 230000009286 beneficial effect Effects 0.000 description 1
- 239000002826 coolant Substances 0.000 description 1
- 238000001816 cooling Methods 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 230000004992 fission Effects 0.000 description 1
- 230000004927 fusion Effects 0.000 description 1
- 229910021389 graphene Inorganic materials 0.000 description 1
- 238000002372 labelling Methods 0.000 description 1
- 238000012417 linear regression Methods 0.000 description 1
- 230000007774 longterm Effects 0.000 description 1
- 238000012544 monitoring process Methods 0.000 description 1
- 230000003287 optical effect Effects 0.000 description 1
- 238000000611 regression analysis Methods 0.000 description 1
- 230000004044 response Effects 0.000 description 1
- 239000000523 sample Substances 0.000 description 1
- 230000035945 sensitivity Effects 0.000 description 1
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 1
Landscapes
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The present application relates to a method, an apparatus, a computer device, a storage medium and a computer program product for nuclear power measurement. The method comprises the steps of receiving a nuclear power measurement value and a thermal power measurement value of a nuclear reactor core in real time, obtaining a first nuclear power measurement value and a second thermal power measurement value of the nuclear reactor core under the condition that the nuclear reactor core is operated to a full power steady state for the first time, and obtaining a second nuclear power measurement value and a second thermal power measurement value of the nuclear reactor core under the condition that the nuclear reactor core is operated to a low power steady state for the first time. And determining a correction coefficient according to the first nuclear power measured value, the first thermal power measured value, the second nuclear power measured value and the second thermal power measured value, and correcting the subsequently received nuclear power measured value according to the correction coefficient to obtain a nuclear power correction value. The method can improve the correction efficiency of the nuclear power measured value.
Description
Technical Field
The present application relates to the field of nuclear reactor off-stack detection technology, and in particular, to a method, an apparatus, a computer device, a storage medium, and a computer program product for correcting a nuclear power measurement value.
Background
In the operation stage of the nuclear reactor, the interior of the reactor core is usually in a high-temperature, high-pressure and high-discharge environment, and the acquisition of important operation parameters such as the whole actual operation power of the reactor core is obtained through detection by detectors arranged on the periphery of the reactor core. However, in the actual running process of the nuclear power plant, working conditions with different powers can appear according to different power grid loads, the number of core neutrons detected by the off-stack detector is changed due to the change of the working conditions, and finally the counting of the off-stack detector is affected, so that the indicating value of the off-stack detector needs to be regularly calibrated, and the indicating value of the off-stack detector is consistent with the parameter change value of the true value in the stack.
At present, for checking the indicated value of the detector outside the reactor of the traditional nuclear reactor, a xenon oscillation method and a one-point method are mainly used, xenon oscillation disturbance calculation is carried out in the reactor, the calibration coefficient is solved, and finally the detector outside the reactor is calibrated.
However, the above solution requires a relatively complex theoretical calculation of the nuclear power measurement, the calibration process is relatively complicated, and at the end of the core life of the nuclear reactor, xenon oscillation is difficult to be performed, which results in low correction efficiency of the nuclear power measurement.
Disclosure of Invention
In view of the foregoing, it is desirable to provide a nuclear detector calibration method, apparatus, computer device, computer readable storage medium, and computer program product that can improve correction efficiency.
In a first aspect, the present application provides a method for correcting a core power measurement. The method comprises the following steps:
receiving nuclear power measurements and thermal power measurements of a nuclear reactor core in real time;
Acquiring a first nuclear power measurement and a second thermal power measurement of the nuclear reactor core when the nuclear reactor core is first operated to a full power steady state, and acquiring a second nuclear power measurement and a second thermal power measurement of the nuclear reactor core when the nuclear reactor core is first operated to a low power steady state;
Determining a correction factor based on the first nuclear power measurement, the first thermal power measurement, the second nuclear power measurement, and the second thermal power measurement;
and correcting the subsequently received nuclear power measured value according to the correction coefficient to obtain a nuclear power correction value.
In one embodiment, determining the correction factor based on the first core power measurement, the first thermal power measurement, the second core power measurement, and the second thermal power measurement comprises:
determining a difference value between the second nuclear power measurement value and the first nuclear power measurement value to obtain a nuclear power measurement difference value;
Determining a difference value between the second thermal power measurement value and the first thermal power measurement value to obtain a thermal power measurement difference value;
and determining a correction coefficient according to the thermal power measurement difference value and the nuclear power measurement difference value.
In one embodiment, the correcting the subsequently received core power measurement value according to the correction coefficient to obtain a core power correction value includes:
obtaining a first difference between the core power measurement and the first core power measurement;
Determining a second difference value between the core power measured value and the first core power measured value according to the first difference value and the correction coefficient, wherein the second difference value is obtained by correcting the first difference value;
And obtaining a nuclear power correction value according to the second difference value and the first thermal power measurement value.
In one embodiment, the method further comprises:
And updating the correction coefficient according to a preset correction coefficient updating condition.
In one embodiment, updating the correction coefficient according to a preset correction coefficient updating condition includes:
Acquiring the operation time of a nuclear reactor;
and if the running time is greater than a preset time threshold, updating the correction coefficient.
In a second aspect, the application further provides a device for correcting the measured value of the nuclear power. The device comprises:
the real-time power receiving module is used for receiving the nuclear power measured value and the thermal power measured value of the nuclear reactor core in real time;
The system comprises a measured value acquisition module, a control module and a control module, wherein the measured value acquisition module is used for acquiring a first nuclear power measured value and a second thermal power measured value of a nuclear reactor core under the condition that the nuclear reactor core is operated to a full power steady state for the first time, and acquiring the second nuclear power measured value and the second thermal power measured value of the nuclear reactor core under the condition that the nuclear reactor core is operated to a low power steady state for the first time;
The correction coefficient determining module is used for determining a correction coefficient according to the first nuclear power measured value, the first thermal power measured value, the second nuclear power measured value and the second thermal power measured value;
and the measured value correction module is used for correcting the subsequently received nuclear power measured value according to the correction coefficient to obtain a nuclear power correction value.
In one embodiment, the correction factor determining module is further configured to determine a difference between the second core power measurement value and the first core power measurement value, to obtain a core power measurement difference value; determining a difference value between the second thermal power measurement value and the first thermal power measurement value to obtain a thermal power measurement difference value; and determining a correction coefficient according to the thermal power measurement difference value and the nuclear power measurement difference value.
In a third aspect, the present application also provides a computer device. The computer device comprises a memory and a processor, wherein the memory stores a computer program, and the processor executes the computer program to realize the steps in the above-mentioned embodiments of the method for correcting the measured value of the nuclear power.
In a fourth aspect, the present application also provides a computer-readable storage medium. The computer readable storage medium has stored thereon a computer program which, when executed by a processor, implements the steps of the above-described embodiments of the method for correcting a measured value of each core power.
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 the above-described embodiments of the method for correcting a core power measurement.
The nuclear power measurement value correction method, the device, the computer equipment, the storage medium and the computer program product are used for obtaining a first nuclear power measurement value and a first thermal power measurement value of the nuclear reactor core in a first full power steady state and a second nuclear power measurement value and a second thermal power measurement value of the nuclear reactor core in a first low power steady state by receiving the nuclear power measurement value and the thermal power measurement value of the nuclear reactor core in real time. Then, according to the first nuclear power measured value, the first thermal power measured value, the second nuclear power measured value and the second thermal power measured value, a correction coefficient is determined, and further, according to the correction coefficient, the subsequently received nuclear power measured value is corrected, so that a more accurate nuclear power correction value can be obtained. Therefore, the correction coefficient can be determined by only acquiring the nuclear power measured value and the thermal power measured value under the first full power steady state and the first low power steady state, and compared with the traditional correction method, the correction coefficient determination process is simpler, complex theoretical calculation is not needed, the nuclear power correction process is simpler and more efficient, and the correction efficiency is improved.
Drawings
FIG. 1 is a diagram of an application environment for a method of correcting a core power measurement in one embodiment;
FIG. 2 is a flow chart of a method for correcting a core power measurement in one embodiment;
FIG. 3 is a flow chart of a method for correcting a core power measurement according to another embodiment;
FIG. 4 is a flow chart of a method for correcting a core power measurement in yet another embodiment;
FIG. 5 is a flow chart of a method for correcting a core power measurement in yet another embodiment;
FIG. 6 is a flow chart of a method of correcting a core power measurement in yet another embodiment;
FIG. 7 is a block diagram of a core power measurement correction device in one embodiment;
FIG. 8 is a block diagram of a nuclear power measurement correction device according to another embodiment;
fig. 9 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.
The method for correcting the nuclear power measurement value provided by the embodiment of the application can be applied to an application environment shown in fig. 1. Wherein the probe 102 is connected to the server 104. The data storage system may store data that the server 104 needs to process. The data storage system may be integrated on the server 104 or may be located on a cloud or other network server.
Specifically, the detector 102 may detect the nuclear power and the thermal power of the nuclear reactor core in real time and upload the detected nuclear power and thermal power to the server 104 in real time. The server 104 obtains a first nuclear power measurement and a first thermal power measurement of the nuclear reactor core at a first full power steady state and a second nuclear power measurement and a second thermal power measurement of the nuclear reactor core at a first low power steady state. The server 104 then determines a correction factor based on the first core power measurement, the first thermal power measurement, the second core power measurement, and the second thermal power measurement. Further, the server 104 corrects the subsequently received core power measurement value according to the correction coefficient, so as to obtain a more accurate core power correction value. It can be understood that the method for correcting the core power measurement value provided by the embodiment of the application can also be applied to a terminal or a system comprising the terminal and a server.
Wherein the detector 102 may be, but is not limited to, various nuclear reactor off-stack detectors. The server 104 may be implemented as a stand-alone server or as a server cluster of multiple servers.
In one embodiment, as shown in fig. 2, a method for correcting a core power measurement value is provided, and the method is applied to the server 104 in fig. 1 for illustration, and includes the following steps:
S200, receiving a nuclear power measurement value and a thermal power measurement value of a nuclear reactor core in real time.
During nuclear reactor operation, nuclear power and thermal power are two key parameters. Where nuclear power is the nuclear energy released per unit time from nuclear fuel in a nuclear reactor, i.e., the nuclear fission or fusion of the nuclei in the nuclear fuel, generates neutrons and releases energy, and is used to describe the rate of release of that energy. Thermal power refers to the rate at which nuclear energy is ultimately transferred to the reactor coolant in the form of thermal energy.
Specifically, the nuclear power measurement value and the thermal power measurement value of the nuclear reactor core can be directly or indirectly detected by an off-stack detector or other power measurement devices, and the off-stack detector or other power measurement devices can feed back the nuclear power measurement value and the thermal power measurement value to a corresponding server or terminal in real time for subsequent correction processing, and can also be displayed on an instrument panel of a control room in real time for technicians to view at any time.
In specific implementation, an off-pile detector can be installed around the nuclear reactor, and can measure the nuclear power and the thermal power of the nuclear reactor core in real time and report the measured nuclear power measured value and the measured thermal power measured value to a server in real time. The server receives the nuclear power measurement value and the thermal power measurement value of the nuclear reactor core reported by the off-stack detector in real time.
S400, acquiring a first nuclear power measurement value and a second thermal power measurement value of the nuclear reactor core when the nuclear reactor core is operated to a full power steady state for the first time, and acquiring the second nuclear power measurement value and the second thermal power measurement value of the nuclear reactor core when the nuclear reactor core is operated to a low power steady state for the first time.
The full power refers to a state that the operating power of the nuclear reactor reaches the rated power thereof, namely, under the condition that components such as a nuclear fuel and a cooling system and the like normally operate, the nuclear reaction is performed at the rated speed, so that the rated power of the nuclear reactor is reached, and the low-power steady state refers to a state that the nuclear reactor is operated under a non-full-power steady state, for example, 80% of the full power, 60% of the full power and the like. During operation of a nuclear reactor, steady state refers to the condition in which the operating state of the nuclear reactor remains relatively unchanged for a certain period of time, and in which various key parameters of the nuclear reactor, such as nuclear power, temperature, pressure, etc., tend to stabilize.
The first nuclear power measurement value and the first thermal power measurement value of the nuclear reactor core in the first full power steady state and the second nuclear power measurement value and the second thermal power measurement value of the nuclear reactor core in the first low power steady state can be directly obtained through the nuclear power measurement value and the thermal power measurement value uploaded in real time by the off-stack detector or other power measurement devices. It should be noted that, when the nuclear reactor core first runs to the full power steady state, it can be considered that the nuclear power and the thermal power collected by the extra-reactor detector or other power measurement devices can accurately reflect the running condition inside the nuclear reactor core. Similarly, when the nuclear reactor core is operated to low power for the first time, it can be considered that the nuclear power and the thermal power collected by the off-core detector or other power measurement devices can accurately reflect the operation condition inside the nuclear reactor core. As such, the nuclear power measurements of the nuclear reactor core during other conditions may be corrected based on the first nuclear power measurement, the first thermal power measurement, the second nuclear power measurement, and the second thermal power measurement collected under the two conditions.
S600, determining a correction factor based on the first core power measurement, the first thermal power measurement, the second core power measurement, and the second thermal power measurement.
The correction factor is used to correct the value indicated for the outer detector so that the indicator value of the outer detector accurately reflects the actual operating state inside the nuclear reactor core.
The indication value of the detector outside the reactor can not accurately reflect the actual operation state of the reactor core under most conditions, and therefore, the real-time nuclear power measured value is a value to be corrected in most times and needs to be corrected through subsequent steps. It is found that the reasons for the deviation of the indication value of the detector outside the reactor from the actual running state inside the reactor core may be the response sensitivity of the detector, the burnup effect, the influence of water temperature, and the like, and the correction modes are different in consideration of the different reasons for the deviation.
In this embodiment, the deviation of the nuclear power and the thermal power indicated by the off-stack detector is mainly considered, so that the correction coefficient may be determined according to the first nuclear power measurement value, the second nuclear power measurement value, the first thermal power measurement value, and the first thermal power measurement value obtained in the above steps. For example, a linear regression method may be used to determine the functional relationship between core power and thermal power and further determine the correction factor.
S800, correcting the subsequently received nuclear power measured value according to the correction coefficient to obtain a nuclear power correction value.
And correcting the subsequently received nuclear power measured value according to the correction coefficient, wherein the correction process can enable the nuclear power measured value to more accurately reflect the actual running state of the nuclear reactor, and obtain the nuclear power correction value. The nuclear power correction values may be used for subsequent analysis of nuclear reactor operating conditions and performance.
According to the nuclear power measurement value correction method, the first nuclear power measurement value and the first thermal power measurement value of the nuclear reactor core in the first full power steady state and the second nuclear power measurement value and the second thermal power measurement value of the nuclear reactor core in the first low power steady state are obtained through receiving the nuclear power measurement value and the thermal power measurement value of the nuclear reactor core in real time. Then, according to the first nuclear power measured value, the first thermal power measured value, the second nuclear power measured value and the second thermal power measured value, a correction coefficient is determined, and further, according to the correction coefficient, the subsequently received nuclear power measured value is corrected, so that a more accurate nuclear power correction value can be obtained. Therefore, the correction coefficient can be determined by only acquiring the nuclear power measured value and the thermal power measured value under the first full power steady state and the first low power steady state, and compared with the traditional correction method, the correction coefficient determination process is simpler, complex theoretical calculation is not needed, the nuclear power correction process is simpler and more efficient, and the correction efficiency is improved.
In one embodiment, as shown in fig. 3, S600 includes:
s620, determining a difference value between the second core power measurement value and the first core power measurement value to obtain a core power measurement difference value.
S640, determining a difference value between the second thermal power measured value and the first thermal power measured value to obtain a thermal power measured difference value.
And S660, determining a correction coefficient according to the thermal power measurement difference value and the nuclear power measurement difference value.
In the process of determining the correction coefficient, the running condition of the nuclear reactor under the first full-power steady state and the running condition of the nuclear reactor under the first low-power steady state are considered at the same time. Specifically, it is necessary to determine the difference between the second core power measurement value, the first core power measurement value, and the difference between the second thermal power measurement value and the first thermal power measurement value, and determine the correction coefficient based on the thermal power measurement difference and the core power measurement difference. The formula may be as follows:
In the method, in the process of the invention, The correction coefficient is represented by a number of coefficients,A second thermal power measurement is indicated,A first thermal power measurement value is represented,Representing a second core power measurement value,Representing a first core power measurement.
In this embodiment, the difference between the second core power measurement value and the first core power measurement value is determined to obtain a core power measurement difference value, and the difference between the second thermal power measurement value and the first thermal power measurement value is determined to obtain a thermal power measurement difference value, and then the correction coefficient is determined according to the thermal power measurement difference value and the core power measurement difference value. In the determination process of the correction coefficient, the nuclear power and the thermal power of the nuclear reactor in different states are considered at the same time, so that the deviation between the nuclear power and the thermal power can be effectively corrected, and the indicated value of the off-core detector can be more similar to the real running condition inside the reactor core of the nuclear reactor.
In one embodiment, as shown in fig. 4, S800 includes:
s820, obtaining a first difference value between the core power measured value and the first core power measured value.
And S840, determining a second difference value between the core power measured value and the first core power measured value according to the first difference value and the correction coefficient, wherein the second difference value is obtained by correcting the first difference value.
S860, obtaining a nuclear power correction value according to the second difference value and the first thermal power measurement value.
With the above embodiment, after the correction coefficient is determined, the indication value of the off-stack detector needs to be corrected using the correction coefficient. Specifically, a nuclear power measured value detected by the off-stack detector is obtained, a first difference value between the nuclear power measured value and the first nuclear power measured value is determined, and the first difference value is corrected by using the correction coefficient to obtain a second difference value. Further, a core power correction value is determined based on the second difference core first thermal power measurement. The specific formula is as follows:
wherein, For the correction value of the core power,As a result of the nuclear power measurements,As a first core power measurement value,Is a first thermal power measurement.
The above described modifications are applicable to multiple phases of a nuclear reactor, including a low power operating state and a return to a full power operating state again. When the nuclear reactor returns to the full power operation state again, the nuclear power measured value at the moment is very close to the first nuclear power measured value, namely the correction amount is very small and can be ignored, and the indication value of the detector outside the reactor at the moment can be considered to reflect the operation state inside the reactor core more accurately.
In this embodiment, the real-time core power correction value may be obtained by obtaining a first difference between the core power measurement value and the first core power measurement value, and then determining a second difference between the core power measurement value and the first core power measurement value according to the first difference and the correction coefficient, where the second difference is a value obtained by correcting the first difference, and according to the second difference, the first thermal power measurement value is obtained. The whole correction flow improves the real-time monitoring precision of the nuclear power, allows the correction of the nuclear power measured value to be realized in a plurality of stages of the nuclear reactor, and is beneficial to enabling the corrected nuclear power measured value to accurately reflect the running condition of the nuclear reactor core.
In one embodiment, as shown in fig. 5, the core power measurement correction method further includes:
S900, updating the correction coefficient according to a preset correction coefficient updating condition.
The update conditions of the correction coefficients are related to the specific nuclear reaction system, and the update of the correction coefficients aims at adapting to and reflecting the change of the running state of the system so as to improve the correction accuracy.
Illustratively, if a significant change occurs in the configuration or operating conditions of the nuclear reactor, the labeling requires updating the correction coefficients to accommodate the new conditions. The performance of the nuclear reactor may be monitored periodically, and if a deviation in the operating state of the nuclear reactor is found, the correction coefficient may be updated. The update of the correction coefficient may be performed by newly determining the correction coefficient in the correction coefficient determining manner in the above embodiments by using the latest operation data. Furthermore, the correction coefficients may also be updated by continuous fitting using statistical means, such as regression analysis, so that the correction coefficients are more suitable for the current operating state of the nuclear reactor.
In this embodiment, the correction coefficient is updated according to a preset correction coefficient updating condition, so that the adaptability of the correction coefficient to different nuclear reactor operation conditions can be improved, and the efficiency and the accuracy of the correction process can be improved.
In one embodiment, as shown in fig. 6, S900 includes:
S920, acquiring the operation duration of the nuclear reactor.
S940, if the running time length is greater than a preset time length threshold value, updating the correction coefficient.
The operation time of the nuclear reactor is one of conditions for determining whether the correction coefficient needs to be updated. The operation time of the nuclear reactor may be a total operation time from the start-up of the nuclear reactor to the current time. And acquiring the operation time length of the nuclear reactor, setting a time length threshold, and updating the correction coefficient if the operation time length is greater than a preset time length threshold. For example, the duration threshold is set to 7 days, within which the performance of the nuclear reactor core is considered to be relatively small with time of operation, and the correction factor remains applicable, so that no update of the correction factor is required. If the operating time of the nuclear reactor is greater than or equal to 7 days, the performance of the nuclear reactor may have changed, resulting in the correction factor not being applicable to the current nuclear reactor, and thus requiring an update of the correction factor.
The above operation is because the performance of the nuclear reactor may change with the lapse of operation time, such as burnup effect, equipment aging, etc., which may result in that the original correction coefficient may no longer be adapted to the current state of the nuclear reactor, i.e., the correction of the indication value of the off-stack detector is no longer accurate, and thus the correction coefficient needs to be updated. In this embodiment, by acquiring the operation duration of the nuclear reactor, if the operation duration is greater than a preset duration threshold, the correction coefficient is updated, so that the correction coefficient can adapt to the long-term operation change of the nuclear reactor, and the effectiveness of the correction coefficient is improved, thereby improving the accuracy of the efficiency of the correction process.
In order to make a more clear description of the method for correcting a measured value of nuclear power provided by the present application, a specific embodiment is described below with reference to fig. 6, and the specific embodiment includes the following steps:
S200, receiving a nuclear power measurement value and a thermal power measurement value of a nuclear reactor core in real time.
S400, acquiring a first nuclear power measurement value and a second thermal power measurement value of the nuclear reactor core when the nuclear reactor core is operated to a full power steady state for the first time, and acquiring the second nuclear power measurement value and the second thermal power measurement value of the nuclear reactor core when the nuclear reactor core is operated to a low power steady state for the first time.
S620, determining a difference value between the second core power measurement value and the first core power measurement value to obtain a core power measurement difference value.
S640, determining a difference value between the second thermal power measured value and the first thermal power measured value to obtain a thermal power measured difference value.
And S660, determining a correction coefficient according to the thermal power measurement difference value and the nuclear power measurement difference value.
S820, obtaining a first difference value between the core power measured value and the first core power measured value.
And S840, determining a second difference value between the core power measured value and the first core power measured value according to the first difference value and the correction coefficient, wherein the second difference value is obtained by correcting the first difference value.
S860, obtaining a nuclear power correction value according to the second difference value and the first thermal power measurement value.
S920, acquiring the operation duration of the nuclear reactor.
S940, if the running time length is greater than a preset time length threshold value, updating the correction coefficient.
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 device for correcting the nuclear power measured value, which is used for realizing the method for correcting the nuclear power measured value. The implementation of the solution provided by the device is similar to the implementation described in the above method, so the specific limitation in the embodiments of the device for correcting a core power measurement value provided below may be referred to the limitation of the method for correcting a core power measurement value hereinabove, and will not be described herein.
In one embodiment, as shown in fig. 7, there is provided a core power measurement correction apparatus 700, comprising: a real-time power receiving module 710, a measured value obtaining module 720, a correction factor determining module 730, and a measured value correcting module 740, wherein:
A real-time power receiving module 710 for receiving in real-time nuclear power measurements and thermal power measurements of a nuclear reactor core;
The measured value obtaining module 720 is configured to obtain a first nuclear power measured value and a second thermal power measured value of the nuclear reactor core when the nuclear reactor core first operates to a full power steady state, and obtain a second nuclear power measured value and a second thermal power measured value of the nuclear reactor core when the nuclear reactor core first operates to a low power steady state.
A correction factor determining module 730, configured to determine a correction factor according to the first core power measurement value, the first thermal power measurement value, the second core power measurement value, and the second thermal power measurement value;
and the measured value correction module 740 is configured to correct the subsequently received core power measured value according to the correction coefficient to obtain a core power correction value.
In one embodiment, the correction factor determining module 730 is further configured to determine a difference between the second core power measurement value and the first core power measurement value, to obtain a core power measurement difference value. And determining a difference value between the second thermal power measurement value and the first thermal power measurement value to obtain a thermal power measurement difference value, and determining a correction coefficient according to the thermal power measurement difference value and the nuclear power measurement difference value.
In one embodiment, the measurement value correction module 740 is further configured to obtain a first difference value between the core power measurement value and the first core power measurement value, determine a second difference value between the core power measurement value and the first core power measurement value according to the first difference value and the correction coefficient, where the second difference value is a value obtained by correcting the first difference value, and obtain the core power correction value according to the second difference value and the first thermal power measurement value.
In one embodiment, as shown in fig. 8, the core power measurement value correction apparatus 700 further includes a correction coefficient update module 750, where the correction coefficient update module 750 is configured to update the correction coefficient according to a preset correction coefficient update condition.
In one embodiment, the correction factor updating module 750 is further configured to obtain an operation duration of the nuclear reactor, and update the correction factor if the operation duration is greater than a preset duration threshold.
The respective modules in the above-described nuclear power measurement value correction apparatus 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 equipment is used for storing data such as real-time nuclear power measured values, correction coefficients and the like. 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 is executed by a processor to implement a method of correcting a core power measurement.
It will be appreciated by persons skilled in the art that the architecture shown in fig. 9 is merely a block diagram of some of the architecture relevant to the present inventive arrangements and is not limiting as to the computer device to which the present inventive arrangements are applicable, 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, including a memory and a processor, the memory storing a computer program, the processor implementing the steps of the above-described embodiments of the method for correcting a core power measurement when the computer program is executed.
In one embodiment, a computer readable storage medium is provided, on which a computer program is stored which, when executed by a processor, implements the steps of the above-described embodiments of the method for correcting a core power measurement.
In one embodiment, a computer program product is provided, comprising a computer program which, when executed by a processor, implements the steps of the above-described embodiments of the method for correcting a core power measurement.
It should be noted that, the user information (including but not limited to user equipment information, user personal information, etc.) and the data (including but not limited to data for analysis, stored data, presented data, etc.) related to the present application are information and data authorized by the user or sufficiently authorized by each party, and the collection, use and processing of the related data need to comply with the related laws and regulations and standards of the related country and region.
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 correcting a nuclear power measurement, the method comprising:
receiving nuclear power measurements and thermal power measurements of a nuclear reactor core in real time;
Acquiring a first nuclear power measurement and a second thermal power measurement of the nuclear reactor core when the nuclear reactor core is first operated to a full power steady state, and acquiring a second nuclear power measurement and a second thermal power measurement of the nuclear reactor core when the nuclear reactor core is first operated to a low power steady state;
Determining a correction factor based on the first nuclear power measurement, the first thermal power measurement, the second nuclear power measurement, and the second thermal power measurement;
and correcting the subsequently received nuclear power measured value according to the correction coefficient to obtain a nuclear power correction value.
2. The method of claim 1, wherein the determining a correction factor based on the first core power measurement, the first thermal power measurement, the second core power measurement, and the second thermal power measurement comprises:
determining a difference value between the second nuclear power measurement value and the first nuclear power measurement value to obtain a nuclear power measurement difference value;
Determining a difference value between the second thermal power measurement value and the first thermal power measurement value to obtain a thermal power measurement difference value;
and determining a correction coefficient according to the thermal power measurement difference value and the nuclear power measurement difference value.
3. The method of claim 1, wherein correcting the subsequently received core power measurement based on the correction factor to obtain a core power correction value comprises:
obtaining a first difference between the core power measurement and the first core power measurement;
Determining a second difference value between the core power measured value and the first core power measured value according to the first difference value and the correction coefficient, wherein the second difference value is obtained by correcting the first difference value;
And obtaining a nuclear power correction value according to the second difference value and the first thermal power measurement value.
4. A method according to any one of claims 1 to 3, characterized in that the method further comprises:
And updating the correction coefficient according to a preset correction coefficient updating condition.
5. A method according to any one of claims 1 to 3, wherein updating the correction factor according to a preset correction factor updating condition comprises:
Acquiring the operation time of a nuclear reactor;
and if the running time is greater than a preset time threshold, updating the correction coefficient.
6. A nuclear power measurement correction device, the device comprising:
the real-time power receiving module is used for receiving the nuclear power measured value and the thermal power measured value of the nuclear reactor core in real time;
The system comprises a measured value acquisition module, a control module and a control module, wherein the measured value acquisition module is used for acquiring a first nuclear power measured value and a second thermal power measured value of a nuclear reactor core under the condition that the nuclear reactor core is operated to a full power steady state for the first time, and acquiring the second nuclear power measured value and the second thermal power measured value of the nuclear reactor core under the condition that the nuclear reactor core is operated to a low power steady state for the first time;
The correction coefficient determining module is used for determining a correction coefficient according to the first nuclear power measured value, the first thermal power measured value, the second nuclear power measured value and the second thermal power measured value;
and the measured value correction module is used for correcting the subsequently received nuclear power measured value according to the correction coefficient to obtain a nuclear power correction value.
7. The apparatus of claim 6, wherein the correction factor determination module is further configured to determine a difference between the second core power measurement and the first core power measurement to obtain a core power measurement difference; determining a difference value between the second thermal power measurement value and the first thermal power measurement value to obtain a thermal power measurement difference value; and determining a correction coefficient according to the thermal power measurement difference value and the nuclear power measurement difference value.
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 one of claims 1 to 5 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 5.
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 according to any one of claims 1 to 5.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202410049075.2A CN117936138A (en) | 2024-01-12 | 2024-01-12 | Nuclear power measured value correction method, device, computer equipment and storage medium |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202410049075.2A CN117936138A (en) | 2024-01-12 | 2024-01-12 | Nuclear power measured value correction method, device, computer equipment and storage medium |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN117936138A true CN117936138A (en) | 2024-04-26 |
Family
ID=90762568
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN202410049075.2A Pending CN117936138A (en) | 2024-01-12 | 2024-01-12 | Nuclear power measured value correction method, device, computer equipment and storage medium |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN117936138A (en) |
-
2024
- 2024-01-12 CN CN202410049075.2A patent/CN117936138A/en active Pending
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN109830317B (en) | Reactor core power intrinsic orthogonal decomposition online reconstruction method based on tracking calculation | |
| JP2023525946A (en) | METHOD AND SYSTEM FOR ERROR ANALYSIS OF MEASURED AREA BASED ON SINGLE LOAD JUMP, AND STORAGE MEDIUM | |
| CN111951988B (en) | Method and device for detecting abnormity of main water supply flow and computer equipment | |
| CN111982245B (en) | Main steam flow calibration method, device, computer equipment and storage medium | |
| CN114047472B (en) | Metering error monitoring system of intelligent ammeter and monitoring method and device thereof | |
| CN110728008B (en) | Method and device for determining expected service life of intelligent ammeter | |
| CN110175935A (en) | Nuclear power data monitoring method, device, computer equipment and storage medium | |
| CN108877969B (en) | Nuclear power theoretical model establishing and verifying method, system and terminal equipment | |
| CN117936138A (en) | Nuclear power measured value correction method, device, computer equipment and storage medium | |
| CN114242280B (en) | Reactor reactivity measuring method, device, equipment and storage medium | |
| CN110749919A (en) | Method and device for calibrating nuclear reactor out-of-pile detector | |
| CN114662281A (en) | Reactor on-line protection method and system and readable storage medium | |
| KR101444794B1 (en) | Method for Constructing the Pseudo Hot Pin Power Distribution Using Detector-Signal-Based Planar Radial Peaking Factor in COLSS | |
| CN112286830A (en) | Testing method and device of electrical measuring instrument, computer equipment and storage medium | |
| CN115954122B (en) | Nuclear reactor pressure vessel fatigue state monitoring method, equipment and device | |
| CN113077105B (en) | Long-false-day load prediction method and device | |
| CN117153438A (en) | Method and device for determining value of control rod of nuclear reactor and computer equipment | |
| JPH09211177A (en) | Performance prediction and surveillance device and prediction method for reactor core using mixed oxide fuel | |
| CN117976273A (en) | Data correction method and device for nuclear reactor core and computer equipment | |
| CN118093306A (en) | Software detection method, device, apparatus, storage medium and program product | |
| JP2002202395A (en) | Reactor power measurement device | |
| CN113626992B (en) | Estimation method and device for characteristic parameters of venturi tube and computer equipment | |
| CN117198572B (en) | Nuclear fuel cladding damage online monitoring method based on POD and neutron detection data | |
| JP2000162364A (en) | Device for calculating reactor core performance of reactor | |
| CN117747157A (en) | Nuclear reactor data correction method, device, computer equipment and storage medium |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| PB01 | Publication | ||
| PB01 | Publication | ||
| SE01 | Entry into force of request for substantive examination | ||
| SE01 | Entry into force of request for substantive examination |