阅读说明：本技术 核电站压水反应堆通量图数据修正方法、装置和终端设备 (Method and device for correcting flux map data of nuclear power station pressurized water reactor and terminal equipment ) 是由 李文 郭远熊 易林 于 2021-07-16 设计创作，主要内容包括：本申请涉及反应堆控制及保护技术领域,特别涉及一种核电站压水反应堆通量图数据修正方法、装置和终端设备,包括：根据待修正的第一通量图数据,确定第一堆芯评价结果；根据历史时间的第二通量图数据,确定修正因子；根据所述修正因子,对所述第一堆芯评价结果进行修正,确定第一修正堆芯评价结果；根据所述第一修正堆芯评价结果,确定修正后的第一通量图数据。本申请实施例通过在正常通道数量不满足要求时对待修正的第一通量图数据进行修正,实现了快速完成全堆芯通量图测量,从而在安全运行的前提下提高了核电机组的发电能力。(The application relates to the technical field of reactor control and protection, in particular to a method, a device and terminal equipment for correcting flux map data of a pressurized water reactor of a nuclear power station, wherein the method comprises the following steps: determining a first core evaluation result according to the first flux map data to be corrected; determining a correction factor according to the second flux map data of the historical time; correcting the first core evaluation result according to the correction factor to determine a first corrected core evaluation result; and determining corrected first flux map data according to the first corrected core evaluation result. According to the embodiment of the application, the first flux map data to be corrected are corrected when the number of the normal channels does not meet the requirement, so that the flux map measurement of the whole reactor core is completed quickly, and the power generation capacity of the nuclear power unit is improved on the premise of safe operation.)

1. A nuclear power station pressurized water reactor flux map data correction method is characterized by comprising the following steps:

determining a first core evaluation result according to the first flux map data to be corrected;

determining a correction factor according to the second flux map data of the historical time;

correcting the first core evaluation result according to the correction factor to determine a first corrected core evaluation result;

and determining corrected first flux map data according to the first corrected core evaluation result.

2. The nuclear power plant reactor flux map data modification method of claim 1, wherein the step of determining the modification factor based on the second flux map data over historical time includes:

determining a second core evaluation result according to the second flux map data of the historical time;

rejecting fault channel data based on the second flux map data, and determining third flux map data;

determining a third core evaluation result according to the third flux map data;

and determining the correction factor according to the second core evaluation result and the third core evaluation result.

3. The nuclear power plant reactor flux map data modification method of claim 2, wherein the step of culling the faulty channel data based on the second flux map data, and prior to determining the third flux map data, further comprises:

determining a normal channel according to the first flux map data;

subtracting the normal channels from all the measurement channels to obtain fault channels;

and determining fault channel data corresponding to the fault channel according to the second traffic map data.

4. The method of nuclear power plant reactor flux map data modification of claim 2, wherein determining a modification factor based on the second core evaluation and the third core evaluation comprises:

calculating a ratio of the second core evaluation result and the third core evaluation result;

and comparing the ratio with 1, and selecting a smaller number as the correction factor.

5. The nuclear power plant pressurized water reactor flux map data correcting method of claim 4, the second core evaluation result being a second maximum component power deviation, the third core evaluation result being a third maximum component power deviation, the correction factor being a maximum component power deviation correction factor;

and/or the presence of a gas in the gas,

the second core evaluation result is a second maximum core quadrant inclination, the third core evaluation result is a third maximum core quadrant inclination, and the correction factor is a maximum core quadrant inclination correction factor;

and/or the presence of a gas in the gas,

the second core evaluation result is a second core enthalpy rise factor, the third core evaluation result is a second core enthalpy rise factor, and the correction factor is a core enthalpy rise factor correction factor;

and/or the presence of a gas in the gas,

the second core evaluation result is a third core hot spot factor, the third core evaluation result is a third core hot spot factor, and the correction factor is a core hot spot factor correction factor.

6. The nuclear power plant reactor flux map data modification method of claim 1, wherein modifying the first core evaluation result based on the modification factor to determine a first modified core evaluation result comprises:

determining a product of the correction factor and the first core evaluation result as the first corrected core evaluation result.

7. The nuclear power plant reactor flux map data modification method of claim 6, wherein the first core evaluation result is a first maximum component power deviation, the correction factor is a maximum component power deviation correction factor, and the first modified core evaluation result is a modified maximum component power deviation;

and/or the presence of a gas in the gas,

the first core evaluation result is a first maximum core quadrant inclination, the correction factor is a maximum core quadrant inclination correction factor, and the first corrected core evaluation result is a corrected maximum core quadrant inclination;

and/or the presence of a gas in the gas,

the first core evaluation result is a first core enthalpy rise factor, the correction factor is a core enthalpy rise factor correction factor, and the first corrected core evaluation result is a corrected core enthalpy rise factor;

and/or the presence of a gas in the gas,

the first core evaluation result is a first core hot spot factor, the correction factor is a core hot spot factor correction factor, and the first corrected core evaluation result is a corrected core hot spot factor.

8. A nuclear power plant pressurized water reactor flux map data correcting apparatus, comprising:

the first stacking core evaluation result determining module is used for determining a first stacking core evaluation result according to the first flux map data to be corrected;

the correction factor module is used for determining a correction factor according to the second flux map data of the historical time;

the first correction module is used for correcting the first core evaluation result according to the correction factor and determining a first corrected core evaluation result;

and the second correction module is used for determining the corrected first flux map data according to the first corrected core evaluation result.

9. The nuclear power plant pressurized water reactor flux map data modification apparatus of claim 8, wherein the modifier module is further configured to:

determining a second core evaluation result according to the second flux map data of the historical time;

rejecting fault channel data based on the second flux map data, and determining third flux map data;

determining a third core evaluation result according to the third flux map data;

and determining the correction factor according to the second core evaluation result and the third core evaluation result.

10. The nuclear power plant reactor flux map data modification apparatus of claim 8, wherein the first modification module is further configured to:

determining a product of the correction factor and the first core evaluation result as the first corrected core evaluation result.

11. A terminal device comprising a memory, a processor and a computer program stored in the memory and executable on the processor, wherein the processor when executing the computer program implements a nuclear power plant reactor pressure flux map data modification method according to any one of claims 1 to 7.

12. A computer-readable storage medium, characterized in that the computer-readable storage medium stores a computer program which, when executed by a processor, implements the nuclear power plant pressurized water reactor flux map data modification method of any one of claims 1 to 7.

Technical Field

The application relates to the technical field of reactor control and protection, in particular to a method and a device for correcting flux map data of a pressurized water reactor of a nuclear power station and terminal equipment.

Background

The three-dimensional power distribution in the reactor core needs to be monitored periodically or on line in real time through a reactor core measuring system during the operation process of the reactor core so as to verify the operation controllability and safety of the reactor core. The core measurement system includes three functions: and measuring the neutron flux distribution in the reactor core, the temperature of the reactor coolant at the outlet of the fuel assembly and the water level in the pressure vessel. The probe of the core measurement system passes through the instrumentation tube to measure the flux distribution of the core, and the measurement process is also called flux map.

The operating specifications of the pressurized water reactor unit require that a full core flux map measurement is completed every 30 equivalent full power days for evaluating the core design and that the safety parameters meet the criteria, if the flux map measurement cannot be completed on schedule, the unit must reduce the power to a power level lower than 50% Pn within 24 hours, and adjust the high-flux automatic shutdown protection constant value to 55% Pn. The flux map measurement requires that the number of the measured normal channels is not less than the preset number under the normal condition, but the fault of the reactor core measurement system may cause that the number of the measured normal channels is less than the preset number, so a method for rapidly completing the flux map measurement of the whole reactor core is urgently needed to solve the problem that the number of the normal channels does not meet the requirement.

Disclosure of Invention

The embodiment of the application provides a method, a device and terminal equipment for correcting flux map data of a nuclear power station pressurized water reactor, and can solve the problem that the flux map measurement of a full core is difficult to complete quickly when the number of normal channels does not meet the requirement.

In a first aspect, an embodiment of the present application provides a nuclear power station pressurized water reactor flux map data correction method, including:

determining a first core evaluation result according to the first flux map data to be corrected;

determining a correction factor according to the second flux map data of the historical time;

correcting the first core evaluation result according to the correction factor to determine a first corrected core evaluation result;

and determining corrected first flux map data according to the first corrected core evaluation result.

In a second aspect, an embodiment of the present application provides a nuclear power station pressurized water reactor flux map data correction apparatus, including:

the first stacking core evaluation result determining module is used for determining a first stacking core evaluation result according to the first flux map data to be corrected;

the correction factor module is used for determining a correction factor according to the second flux map data of the historical time;

the first correction module is used for correcting the first core evaluation result according to the correction factor and determining a first corrected core evaluation result;

and the second correction module is used for determining the corrected first flux map data according to the first corrected core evaluation result.

In a third aspect, an embodiment of the present application provides a terminal device, a memory, a processor, and a computer program stored in the memory and executable on the processor, where the processor implements the nuclear power plant pressurized water reactor flux map data modification method of any one of the first aspect when executing the computer program.

In a fourth aspect, the present application provides a computer program product, which when run on a terminal device, causes the terminal device to execute the nuclear power plant pressurized water reactor flux map data correction method according to any one of the first aspect.

In a fifth aspect, the present application provides a computer-readable storage medium, which stores a computer program, and when the computer program is executed by a processor, the method for modifying nuclear power plant pressurized water reactor flux map data according to any one of the first aspect is described above.

It is understood that the beneficial effects of the second aspect to the fifth aspect can be referred to the related description of the first aspect, and are not described herein again.

Compared with the prior art, the embodiment of the application has the advantages that:

the embodiment of the application provides a method, a device and terminal equipment for correcting flux map data of a nuclear power station pressurized water reactor, and the method comprises the following steps: determining a first core evaluation result according to the first flux map data to be corrected; determining a correction factor according to the second flux map data of the historical time; correcting the first core evaluation result according to the correction factor to determine a first corrected core evaluation result; and determining corrected first flux map data according to the first corrected core evaluation result. According to the embodiment of the application, the first flux map data to be corrected are corrected when the number of the normal channels does not meet the requirement, so that the flux map measurement of the whole reactor core is completed quickly, and the power generation capacity of the nuclear power unit is improved on the premise of safe operation.

Drawings

In order to more clearly illustrate the technical solutions in the embodiments of the present application, the drawings needed to be used in the embodiments or the prior art descriptions will be briefly described below, and it is obvious that the drawings in the following description are only some embodiments of the present application, and it is obvious for those skilled in the art to obtain other drawings based on these drawings without inventive exercise.

FIG. 1 is a schematic flow chart diagram of a method for modifying nuclear power plant reactor flux map data according to an embodiment of the present application;

FIG. 2 is a schematic structural diagram of a nuclear power plant pressurized water reactor flux map data correction device provided by an embodiment of the application;

fig. 3 is a schematic structural diagram of a terminal device according to an embodiment of the present application.

Detailed Description

In the following description, for purposes of explanation and not limitation, specific details are set forth, such as particular system structures, techniques, etc. in order to provide a thorough understanding of the embodiments of the present application. It will be apparent, however, to one skilled in the art that the present application may be practiced in other embodiments that depart from these specific details. In other instances, detailed descriptions of well-known systems, devices, circuits, and methods are omitted so as not to obscure the description of the present application with unnecessary detail.

It will be understood that the terms "comprises" and/or "comprising," when used in this specification and the appended claims, specify the presence of stated features, integers, steps, operations, elements, and/or components, but do not preclude the presence or addition of one or more other features, integers, steps, operations, elements, components, and/or groups thereof.

It should also be understood that the term "and/or" as used in this specification and the appended claims refers to and includes any and all possible combinations of one or more of the associated listed items.

As used in this specification and the appended claims, the term "if" may be interpreted contextually as "when", "upon" or "in response to" determining "or" in response to detecting ". Similarly, the phrase "if it is determined" or "if a described condition or event is detected" may be interpreted, depending on the context, to mean "upon determining" or "in response to determining" or "upon detecting a described condition or event" or "in response to detecting a described condition or event".

Furthermore, in the description of the present application and the appended claims, the terms "first," "second," "third," and the like are used for distinguishing between descriptions and not necessarily for describing or implying relative importance.

Reference throughout this specification to "one embodiment" or "some embodiments," or the like, means that a particular feature, structure, or characteristic described in connection with the embodiment is included in one or more embodiments of the present application. Thus, appearances of the phrases "in one embodiment," "in some embodiments," "in other embodiments," or the like, in various places throughout this specification are not necessarily all referring to the same embodiment, but rather "one or more but not all embodiments" unless specifically stated otherwise. The terms "comprising," "including," "having," and variations thereof mean "including, but not limited to," unless expressly specified otherwise.

The technical solutions provided in the embodiments of the present application are explained in detail below.

Referring to fig. 1, a schematic block flow diagram of a nuclear power plant reactor flux map data modification method is shown, which may include the steps of:

step S101: and determining a first core evaluation result according to the first flux map data to be corrected.

The first flux map data includes measurement data corresponding to channels that can be measured normally, in this embodiment, a channel that can be measured normally is referred to as a normal channel, and a channel that cannot be measured normally is referred to as a fault channel, and the normal channel and the fault channel are added to form a total measurement channel.

Optionally, processing and analyzing the first flux MAP data using core data processing software to determine a first core evaluation result, wherein the first core evaluation result comprises a first maximum assembly power deviation MAP_{n (first threshold +)}First maximum core quadrant inclination DA_{n (first threshold +)}First stacking core enthalpy rise factor FDH_{n (first threshold +)}First core hot spot factor QTZ_{n (first threshold +)}At least one item of (1).

Optionally, step S101 includes: judging whether the first flux map data meet the correction condition:

the number of the normal channels is smaller than a first threshold value, the correction condition is not met, and the reactor core measuring system needs to be maintained as soon as possible;

the number of the normal channels is smaller than a first threshold value, larger than the first threshold value and smaller than a second threshold value, the fault channel can be maintained, and the measurement can be continued after the maintenance;

and if the number of the normal channels is greater than the first threshold and less than the second threshold, and the fault channel can not be maintained temporarily, the correction condition is met, namely the number of the normal channels corresponding to the first flux map data to be corrected is greater than the first threshold and less than the second threshold, wherein the first threshold is less than the second threshold, and the specific numerical value is determined according to the actual condition of the reactor. For example, the first threshold value is 35 and the second threshold value is 40.

Step S102: determining a correction factor according to the second flux map data of the historical time, which specifically comprises the following steps:

step S1021: determining a second core evaluation result according to the second flux map data of the historical time;

the second traffic map data is measured in historical time, the number of normal channels corresponding to the second traffic map data needs to be larger than a second threshold, and only when the number of normal channels is larger than the second threshold, the normal situation that the normal channels are successfully measured can be considered to be used for determining the correction factor.

Optionally, the historical time corresponding to the second flux map data is closest to the measurement time corresponding to the first flux map data, so as to be closer to the real condition of the reactor.

Similarly, optionally, processing and analyzing the second flux MAP data using core data processing software to determine a second core evaluation result, wherein the second core evaluation result comprises a second maximum assembly power deviation MAP_{n-1 (second threshold +)}Quadrant inclination of the second largest coreOblique DA_{n-1 (second threshold +)}Second core enthalpy rise factor FDH_{n-1 (second threshold +)}Second core hot spot factor QTZ_{n-1 (second threshold +)}At least one item of (1).

Step S1022: and rejecting fault channel data based on the second flux map data, and determining third flux map data.

Before step S1022, the method further includes: determining fault channel data, and the specific steps comprise:

determining a normal channel according to the first flux map data;

subtracting the normal channels from all the measurement channels to obtain fault channels;

and determining fault channel data corresponding to the fault channel according to the second traffic map data.

Optionally, when the faulty channel data is rejected based on the second flux map data, the faulty channel data may be rejected manually or by a software instruction, which is not specifically limited in the present application.

Step S1023: determining a third core evaluation result according to the third flux map data;

similarly, optionally, processing and analyzing the third flux MAP data using core data processing software to determine a third core evaluation result, wherein the third core evaluation result comprises a third maximum assembly power deviation MAP_{n-1 (first threshold +)}Third maximum core quadrant inclination DA_{n-1 (first threshold +)}Third core enthalpy rise factor FDH_{n-1 (first threshold +)}Third core hot spot factor QTZ_{n-1 (first threshold +)}At least one item of (1).

Step S1024: and determining a correction factor according to the second core evaluation result and the third core evaluation result.

Optionally, the second core evaluation result is a second maximum assembly power deviation MAP_{n-1 (second threshold +)}And the third core evaluation result is a third maximum assembly power deviation MAP_{n-1 (first threshold +)}The correction factor is a maximum component power deviation correction factor K_MAP；

And/or the presence of a gas in the gas,

the second core evaluation result is the second maximum core quadrant inclination DA_{n-1 (second threshold +)}And the third core evaluation result is a third maximum core quadrant inclination DA_{n-1 (first threshold +)}The correction factor is a maximum reactor core quadrant inclination correction factor K_DA；

And/or the presence of a gas in the gas,

the second core evaluation result is a second core enthalpy rise factor FDH_{n-1 (second threshold +)}The third core evaluation result is a third core enthalpy rise factor FDH_{n-1 (first threshold +)}The correction factor is a reactor core enthalpy rise factor correction factor K_FDH；

And/or the presence of a gas in the gas,

the second core evaluation result is the core hot spot factor QTZ_{n-1 (second threshold +)}The third core evaluation result is a third core hot spot factor QTZ_{n-1 (first threshold +)}The correction factor is a reactor core hot spot factor correction factor K_QTZ。

Wherein:

K_MAP＝MIN{MAP_{n-1 (second threshold +)}/MAP_{n-1 (first threshold +)}，1}

K_DA＝MIN{DA_{n-1 (second threshold +)}/DAP_{n-1 (first threshold +)}，1}

K_FDH＝MIN{FDH_{n-1 (second threshold +)}/FDH_{n-1 (first threshold +)}，1}

K_QTZ＝MIN{QTZ_{n-1 (second threshold +)}/QTZ_{n-1 (first threshold +)}，1}

Step S103: and correcting the first core evaluation result according to the correction factor to determine a first corrected core evaluation result.

Optionally, the product of the correction factor and the first core evaluation result is determined as the first corrected core evaluation result.

Wherein:

the first core evaluation result is a first maximum component power deviation MAP_{n (first threshold +)}The correction factor is maximumComponent power offset correction factor K_MAPThe first corrected core evaluation result includes the corrected maximum component power deviation MAP ^_{n (first threshold +)}；

And/or the presence of a gas in the gas,

the first core evaluation result is a first maximum core quadrant inclination DA_{n (first threshold +)}The correction factor is a maximum reactor core quadrant inclination correction factor K_DAThe first corrected core evaluation result is the corrected maximum core quadrant inclination DA ^_{n (first threshold +)}；

And/or the presence of a gas in the gas,

the first core evaluation result is a first core enthalpy-rise factor FDH_{n (first threshold +)}The correction factor is a reactor core enthalpy rise factor correction factor K_FDHThe first corrected core evaluation result is corrected core enthalpy rise factor FDH ^_{n (first threshold +)}；

And/or the presence of a gas in the gas,

the first core evaluation result is a first core hot-spot factor QTZ_{n (first threshold +)}The correction factor is a reactor core hot spot factor correction factor K_QTZThe first corrected core evaluation result is corrected core hotspot factor QTZ ^_{n (first threshold +)}。

MAP＾_{n (first threshold +)}＝MAP_{n (first threshold +)}*K_MAP

DA＾_{n (first threshold +)}＝DA_{n (first threshold +)}*K_DA

FDH＾_{n (first threshold +)}＝FDH_{n (first threshold +)}*K_FDH

QTZ＾_{n (first threshold +)}＝QTZ_{n (first threshold +)}*K_QTZ

According to the embodiment of the application, the correction factor is adopted to correct the first flux map data to be corrected when the number of the normal channels does not meet the requirement, the abnormal reactor core parameters can be found in time, the condition that the unreal reactor core parameters exceed the limit due to improper correction is avoided, the phenomenon that the nuclear power unit is forced to introduce the transient reactor core power reduction due to the fact that the measurement of the regular flux map exceeds the limit is avoided, the potential human error and equipment abnormal risk caused by the transient nuclear power unit are reduced, the rapid completion of the measurement of the full reactor core flux map is realized, and the power generation capacity of the nuclear power station is improved on the premise of safe operation.

It should be noted that, within the technical scope of the present disclosure, other sequencing schemes that can be easily conceived by those skilled in the art should also be within the protection scope of the present disclosure, and detailed description is omitted here.

Referring to fig. 2, a schematic diagram of a nuclear power plant pressurized water reactor flux map data correction apparatus according to an embodiment of the present application is shown, where for convenience of description, only a portion related to the embodiment of the present invention is shown, and the apparatus includes:

the first stacking core evaluation result determining module 21 is configured to determine a first stacking core evaluation result according to the first flux map data to be corrected;

a correction factor module 22, configured to determine a correction factor according to the second histogram data of the historical time;

the first correction module 23 is configured to correct the first core evaluation result according to the correction factor, and determine a first corrected core evaluation result;

and a second correction module 24 for determining corrected first flux map data based on the first corrected core evaluation result.

The modifier module 22 is also configured to:

determining a second core evaluation result according to the second flux map data of the historical time;

rejecting fault channel data based on the second flux map data, and determining third flux map data;

determining a third core evaluation result according to the third flux map data;

and determining the correction factor according to the second core evaluation result and the third core evaluation result.

The first modification module 23 is further configured to:

determining a product of the correction factor and the first core evaluation result as the first corrected core evaluation result.

Determining a correction factor based on the second core evaluation and the third core evaluation, comprising:

calculating a ratio of the second core evaluation result and the third core evaluation result;

and comparing the ratio with 1, and selecting a smaller number as the correction factor.

A second corrective module 24 further configured to determine the product of the correction factor and the first core evaluation as the first corrected core evaluation.

Optionally, the second core evaluation result is a second maximum assembly power deviation MAP_{n-1 (second threshold +)}And the third core evaluation result is a third maximum assembly power deviation MAP_{n-1 (first threshold +)}The correction factor is a maximum component power deviation correction factor K_MAP；

And/or the presence of a gas in the gas,

the second core evaluation result is the second maximum core quadrant inclination DA_{n-1 (second threshold +)}And the third core evaluation result is a third maximum core quadrant inclination DA_{n-1 (first threshold +)}The correction factor is a maximum reactor core quadrant inclination correction factor K_DA；

And/or the presence of a gas in the gas,

the second core evaluation result is a second core enthalpy rise factor FDH_{n-1 (second threshold +)}The third core evaluation result is a third core enthalpy rise factor FDH_{n-1 (first threshold +)}The correction factor is a reactor core enthalpy rise factor correction factor K_FDH；

And/or the presence of a gas in the gas,

the second core evaluation result is the core hot spot factor QTZ_{n-1 (second threshold +)}The third core evaluation result is a third core hot spot factor QTZ_{n-1 (first threshold +)}The correction factor is a reactor core hot spot factor correction factor K_QTZ。

Wherein:

K_MAP＝MIN{MAP_{n-1 (second threshold +)}/MAP_{n-1 (first threshold +)}，1}

K_DA＝MIN{DA_{n-1 (second threshold +)}/DAP_{n-1 (first threshold +)}，1}

K_FDH＝MIN{FDH_{n-1 (second threshold +)}/FDH_{n-1 (first threshold +)}，1}

K_QTZ＝MIN{QTZ_{n-1 (second threshold +)}/QTZ_{n-1 (first threshold +)}，1}

Wherein:

the first core evaluation result is a first maximum component power deviation MAP_{n (first threshold +)}The correction factor is a maximum component power deviation correction factor K_MAPThe first corrected core evaluation result includes the corrected maximum component power deviation MAP ^_{n (first threshold +)}；

And/or the presence of a gas in the gas,

the first core evaluation result is a first maximum core quadrant inclination DA_{n (first threshold +)}The correction factor is a maximum reactor core quadrant inclination correction factor K_DAThe first corrected core evaluation result is the corrected maximum core quadrant inclination DA ^_{n (first threshold +)}；

And/or the presence of a gas in the gas,

the first core evaluation result is a first core enthalpy-rise factor FDH_{n (first threshold +)}The correction factor is a reactor core enthalpy rise factor correction factor K_FDHThe first corrected core evaluation result is corrected core enthalpy rise factor FDH ^_{n (first threshold +)}；

And/or the presence of a gas in the gas,

the first core evaluation result is a first core hot-spot factor QTZ_{n (first threshold +)}The correction factor is a reactor core hot spot factor correction factor K_QTZThe first corrected core evaluation result is corrected core hotspot factor QTZ ^_{n (first threshold +)}。

MAP＾_{n (first threshold +)}＝MAP_{n (first threshold +)}*K_MAP

DA＾_{n (first threshold +)}＝DA_{n (first threshold +)}*K_DA

FDH＾_{n (first threshold +)}＝FDH_{n (first threshold +)}*K_FDH

QTZ＾_{n (first threshold +)}＝QTZ_{n (first threshold +)}*K_QTZ

It will be apparent to those skilled in the art that, for convenience and simplicity of description, the foregoing division of the functional modules is merely illustrated, and in practical applications, the above function distribution may be performed by different functional units and modules as needed, that is, the internal structure of the mobile terminal is divided into different functional units or modules to perform all or part of the above described functions. Each functional module in the embodiments may be integrated in one processing unit, or each unit may exist alone physically, or two or more units are integrated in one unit, and the integrated unit may be implemented in a form of hardware, or in a form of software functional unit. In addition, specific names of the functional modules are only used for distinguishing one functional module from another, and are not used for limiting the protection scope of the application. The specific working process of the module in the mobile terminal may refer to the corresponding process in the foregoing method embodiment, and is not described herein again.

Fig. 3 is a schematic diagram of a terminal device according to an embodiment of the present invention. As shown in fig. 3, the terminal device 3 of this embodiment includes: a processor 30, a memory 31 and a computer program 32 stored in said memory 31 and executable on said processor 30. The processor 30, when executing the computer program 32, implements the steps of the nuclear power plant reactor flux map data correction method described above, such as steps 101 to 104 shown in fig. 1. Alternatively, the processor 30, when executing the computer program 32, implements the functions of the modules/units in the above-mentioned device embodiments, such as the functions of the modules 21 to 34 shown in fig. 2.

Illustratively, the computer program 32 may be partitioned into one or more modules/units that are stored in the memory 31 and executed by the processor 30 to implement the present invention. The one or more modules/units may be a series of computer program instruction segments capable of performing specific functions, which are used to describe the execution process of the computer program 32 in the terminal device 3.

The terminal device 3 may be a desktop computer, a notebook, a palm computer, or other computing devices. The terminal device may include, but is not limited to, a processor 30, a memory 31. It will be understood by those skilled in the art that fig. 3 is only an example of the terminal device 3, and does not constitute a limitation to the terminal device 3, and may include more or less components than those shown, or combine some components, or different components, for example, the terminal device may also include an input-output device, a network access device, a bus, etc.

The Processor 30 may be a Central Processing Unit (CPU), other general purpose Processor, a Digital Signal Processor (DSP), an Application Specific Integrated Circuit (ASIC), an off-the-shelf Programmable Gate Array (FPGA) or other Programmable logic device, discrete Gate or transistor logic, discrete hardware components, etc. A general purpose processor may be a microprocessor or the processor may be any conventional processor or the like.

The memory 31 may be an internal storage unit of the terminal device 3, such as a hard disk or a memory of the terminal device 3. The memory 31 may also be an external storage device of the terminal device 3, such as a plug-in hard disk, a Smart Media Card (SMC), a Secure Digital (SD) Card, a Flash memory Card (Flash Card), and the like, which are provided on the terminal device 3. Further, the memory 31 may also include both an internal storage unit and an external storage device of the terminal device 3. The memory 31 is used for storing the computer program and other programs and data required by the terminal device. The memory 31 may also be used to temporarily store data that has been output or is to be output.

The embodiments of the present application further provide a computer-readable storage medium, where a computer program is stored, and when the computer program is executed by a processor, the computer program implements the steps in the above-mentioned method embodiments.

The embodiments of the present application provide a computer program product, which when running on a mobile terminal, enables the mobile terminal to implement the steps in the above method embodiments when executed.

It will be apparent to those skilled in the art that, for convenience and brevity of description, only the above-mentioned division of the functional units and modules is illustrated, and in practical applications, the above-mentioned function distribution may be performed by different functional units and modules according to needs, that is, the internal structure of the apparatus is divided into different functional units or modules to perform all or part of the above-mentioned functions. Each functional unit and module in the embodiments may be integrated in one processing unit, or each unit may exist alone physically, or two or more units are integrated in one unit, and the integrated unit may be implemented in a form of hardware, or in a form of software functional unit. In addition, specific names of the functional units and modules are only for convenience of distinguishing from each other, and are not used for limiting the protection scope of the present invention. The specific working processes of the units and modules in the system may refer to the corresponding processes in the foregoing method embodiments, and are not described herein again.

In the above embodiments, the descriptions of the respective embodiments have respective emphasis, and reference may be made to the related descriptions of other embodiments for parts that are not described or illustrated in a certain embodiment.

Those of ordinary skill in the art will appreciate that the various illustrative elements and algorithm steps described in connection with the embodiments disclosed herein may be implemented as electronic hardware or combinations of computer software and electronic hardware. Whether such functionality is implemented as hardware or software depends upon the particular application and design constraints imposed on the implementation. Skilled artisans may implement the described functionality in varying ways for each particular application, but such implementation decisions should not be interpreted as causing a departure from the scope of the present invention.

In the embodiments provided in the present invention, it should be understood that the disclosed apparatus/terminal device and method may be implemented in other ways. For example, the above-described embodiments of the apparatus/terminal device are merely illustrative, and for example, the division of the modules or units is only one logical division, and there may be other divisions when actually implemented, for example, a plurality of units or components may be combined or integrated into another system, or some features may be omitted, or not executed. In addition, the shown or discussed mutual coupling or direct coupling or communication connection may be an indirect coupling or communication connection through some interfaces, devices or units, and may be in an electrical, mechanical or other form.

The units described as separate parts may or may not be physically separate, and parts displayed as units may or may not be physical units, may be located in one place, or may be distributed on a plurality of network units. Some or all of the units can be selected according to actual needs to achieve the purpose of the solution of the embodiment.

In addition, functional units in the embodiments of the present invention may be integrated into one processing unit, or each unit may exist alone physically, or two or more units are integrated into one unit. The integrated unit can be realized in a form of hardware, and can also be realized in a form of a software functional unit.

The integrated modules/units, if implemented in the form of software functional units and sold or used as separate products, may be stored in a computer readable storage medium. Based on such understanding, all or part of the flow of the method according to the embodiments of the present invention may also be implemented by a computer program, which may be stored in a computer-readable storage medium, and when the computer program is executed by a processor, the steps of the method embodiments may be implemented. Wherein the computer program comprises computer program code, which may be in the form of source code, object code, an executable file or some intermediate form, etc. The computer-readable medium may include: any entity or device capable of carrying the computer program code, recording medium, usb disk, removable hard disk, magnetic disk, optical disk, computer Memory, Read-Only Memory (ROM), Random Access Memory (RAM), electrical carrier wave signals, telecommunications signals, software distribution medium, and the like. It should be noted that the computer readable medium may contain other components which may be suitably increased or decreased as required by legislation and patent practice in jurisdictions, for example, in some jurisdictions, computer readable media which may not include electrical carrier signals and telecommunications signals in accordance with legislation and patent practice.

The above-mentioned embodiments are only used for illustrating the technical solutions of the present invention, and not for limiting the same; although the present invention has been described in detail with reference to the foregoing embodiments, it will be understood by those of ordinary skill in the art that: the technical solutions described in the foregoing embodiments may still be modified, or some technical features may be equivalently replaced; such modifications and substitutions do not substantially depart from the spirit and scope of the embodiments of the present invention, and are intended to be included within the scope of the present invention.