CN117786995A - Method, device, equipment and medium for calculating overall leakage rate of current containment - Google Patents
Method, device, equipment and medium for calculating overall leakage rate of current containment Download PDFInfo
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Abstract
The application relates to the technical field of calculation of the overall leak rate of a current containment, in particular to a method, a device, equipment and a medium for calculating the overall leak rate of the current containment, wherein the method comprises the following steps: detecting local leakage rate data of a leakage component on a containment of the nuclear power plant in response to the current overhaul of the nuclear power plant being a periodic overhaul, and generating a current local leakage rate sum based on the local leakage rate data; acquiring local leakage rate data of the last time of overhaul of the nuclear power station, recording the local leakage rate data as last local leakage rate data, and generating a last local leakage rate sum based on the last local leakage rate data; generating a local leak rate sum difference based on the current local leak rate sum and the last local leak rate sum; acquiring the integral leakage rate of the containment during the overhaul of the nuclear power plant, and recording the integral leakage rate of the containment as the integral leakage rate of the containment; generating a current containment overall leak rate based on the local leak rate sum difference and the last containment overall leak rate; the method and the device are convenient to accurately grasp the overall tightness condition of the containment of the nuclear power station.
Description
Technical Field
The application relates to the technical field of calculation of the overall leak rate of a current containment, in particular to a method, a device, equipment and a medium for calculating the overall leak rate of the current containment.
Background
The containment of the nuclear power plant is the last safety barrier of the nuclear reactor, and in order to ensure the operation safety of the containment of the nuclear power plant, the sealing performance of the containment of the nuclear power plant needs to be detected during the major repair of the nuclear power plant, so that the online operation state of a nuclear power system is conveniently simulated under a reference accident state, and whether the normal sealing performance of the containment of the nuclear power plant can be maintained under the reference accident state is evaluated.
The overhaul of the nuclear power plant is divided into a first overhaul, a predetermined year overhaul (such as periodical ten years overhaul), and a periodic overhaul between the first overhaul and the first ten years overhaul or a periodic overhaul between adjacent ten years overhaul; when the nuclear power station is subjected to primary overhaul or overhaul of a preset age, the whole leakage rate detection and the partial tightness detection are required to be carried out on the containment of the nuclear power station; when the nuclear power station is in regular overhaul, only partial tightness detection is needed for the containment of the nuclear power station, namely, the leakage rate of parts such as penetrating members, air gates and channels arranged on the containment of the nuclear power station is detected.
However, during regular overhauls of a nuclear power plant, only the partial tightness of the containment of the nuclear power plant can be known, but the overall tightness of the containment of the nuclear power plant cannot be known, so that the overall tightness of the containment of the nuclear power plant cannot be accurately grasped every time the nuclear power plant is overhauled.
Disclosure of Invention
In order to facilitate accurate grasping of the overall tightness of a containment of a nuclear power plant during each major repair of the nuclear power plant, the embodiment of the application provides a method, a device, equipment and a medium for calculating the overall leakage rate of the containment.
In a first aspect, an embodiment of the present application provides a method for calculating an overall leak rate of a containment, including:
detecting local leakage rate data of all leakage components on a containment of the nuclear power plant in response to the current overhaul of the nuclear power plant being a periodic overhaul, and generating a current local leakage rate sum based on the local leakage rate data;
acquiring local leakage rate data of the last nuclear power station during overhaul, recording the local leakage rate data as last local leakage rate data, and generating a last local leakage rate sum based on the last local leakage rate data;
generating a local leak rate sum difference based on the current local leak rate sum and the last local leak rate sum;
acquiring the integral leakage rate of the containment during the overhaul of the nuclear power plant, and recording the integral leakage rate of the containment as the integral leakage rate of the containment; and generating a current containment overall leak rate based on the local leak rate sum difference and the last containment overall leak rate.
In a second aspect, embodiments of the present application provide a current containment overall leak rate calculation apparatus, comprising:
the first leakage rate sum calculation module is used for responding to the current overhaul of the nuclear power plant as the periodic overhaul, detecting local leakage rate data of all leakage components on the containment of the nuclear power plant and generating the current local leakage rate sum based on the local leakage rate data;
the second leakage rate sum calculation module is used for acquiring local leakage rate data of the last nuclear power station when the nuclear power station is overhauled, recording the local leakage rate data as last local leakage rate data, and generating last local leakage rate sum based on the last local leakage rate data;
a leakage rate sum difference calculation module configured to generate a local leakage rate sum difference based on the current local leakage rate sum and the last local leakage rate sum;
the integral leakage rate calculation module is used for acquiring the integral leakage rate of the current containment during the overhaul of the nuclear power plant, and recording the integral leakage rate of the containment as the integral leakage rate of the previous containment; and generating a current containment overall leak rate based on the local leak rate sum difference and the last containment overall leak rate.
In a third aspect, embodiments of the present application provide a computer device, where the computer device includes a memory and a processor, where the memory stores a computer program, and where the processor implements steps in the above-described method when executing the computer program.
In a fourth aspect, embodiments of the present application provide a computer-readable storage medium having stored thereon a computer program which, when executed by a processor, performs steps in the above-described method.
In a fifth aspect, embodiments of the present application also provide a computer program product. The computer program product comprises a computer program which, when executed by a processor, implements the steps of any of the method embodiments described above.
In the embodiment of the method, the device, the equipment and the medium for calculating the integral leakage rate of the current containment, when the current overhaul of the nuclear power plant is a regular overhaul, calculating the sum of the local leakage rate data of all leakage components to obtain the current local leakage rate sum; then calculating the sum of the local leakage rate data of all the corresponding leakage components during the previous overhaul of the nuclear power station through historical data to obtain the sum of the local leakage rates of the previous time; then calculating the difference value of the sum of the two local leakage rates, namely the difference value of the current local leakage rate sum and the last local leakage rate sum, so as to obtain a difference value of the local leakage rate sum; then, acquiring the integral leakage rate of the containment during the overhaul of the previous nuclear power station through historical data to obtain the integral leakage rate of the containment last time; then calculating the sum of the sum difference value of the integral leakage rate and the local leakage rate of the last containment, thereby obtaining the integral leakage rate of the current containment of the nuclear power station; so in time this nuclear power station is not carried out the detection of the whole leakage rate of containment when repairing again, still can calculate the whole leakage rate of current containment when repairing this time according to local leakage rate sum total difference and the whole leakage rate of last containment, so be convenient for accurately grasp the whole leakproofness condition of nuclear power station containment when repairing at every turn.
It should be understood that the description of this section is not intended to identify key or critical features of the embodiments of the application or to delineate the scope of the application. Other features of the present application will become apparent from the description that follows.
Drawings
In order to more clearly illustrate the technical solutions of the embodiments of the present invention, the drawings that are needed in the embodiments will be briefly described below, it being understood that the following drawings only illustrate some embodiments of the present invention and therefore should not be considered as limiting the scope, and other related drawings may be obtained according to these drawings without inventive effort for a person skilled in the art.
FIG. 1 is a diagram of an application environment for a current containment overall leak rate calculation method in one embodiment of the present application;
FIG. 2 is a flow chart of a method for calculating the overall leak rate of a containment vessel according to the first embodiment of the present disclosure;
FIG. 3 is a schematic structural diagram of a current containment overall leak rate calculation device according to a second embodiment of the present disclosure;
FIG. 4 is a flowchart of a method for calculating the overall leak rate of a containment vessel according to the third embodiment of the present application;
FIG. 5 is a schematic structural diagram of a current containment overall leak rate calculation device according to a fourth embodiment of the present disclosure;
FIG. 6 is a schematic diagram of a computer device according to one embodiment of the present application;
fig. 7 is an internal structural diagram of a computer-readable storage medium provided in one embodiment of the present application.
Detailed Description
In order to make the objects, technical solutions and advantages of the present disclosure more apparent, the present disclosure will be further described in detail with reference to the accompanying drawings and examples. It should be understood that the specific embodiments described herein are for purposes of illustration only and are not intended to limit the present disclosure.
It should be noted that the terms "first," "second," and the like in the description and claims herein and in the foregoing figures are used for distinguishing between similar objects and not necessarily for describing a particular sequential or chronological order. It is to be understood that the data so used may be interchanged where appropriate such that the embodiments described herein may be capable of operation in sequences other than those illustrated or described herein. Furthermore, the terms "comprises," "comprising," and "having," and any variations thereof, are intended to cover a non-exclusive inclusion, such that a process, method, apparatus, article, or device that comprises a list of steps or elements is not necessarily limited to those steps or elements expressly listed or inherent to such process, method, article, or device.
In this document, the term "and/or" is merely one association relationship describing the associated object, meaning that three relationships may exist. For example, a and/or B may represent: a exists alone, A and B exist together, and B exists alone. In addition, the character "/" herein generally indicates that the front and rear associated objects are an "or" relationship.
To solve the above-mentioned problems, the embodiment of the present disclosure provides a method for calculating the overall leak rate of a containment vessel, which can be applied to an application environment as shown in fig. 1. Wherein the terminal 102 communicates with the server 104 via a network. 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. The terminal 102 may be, but not limited to, various personal computers, notebook computers, smart phones, tablet computers, internet of things devices, and portable wearable devices, where the internet of things devices may be smart speakers, smart televisions, smart air conditioners, smart vehicle devices, and the like. The portable wearable device may be a smart watch, smart bracelet, headset, or the like. The server 104 may be implemented as a stand-alone server or as a server cluster of multiple servers.
Example 1
Fig. 2 is a flowchart of a method for calculating an overall leak rate of a containment, and referring to fig. 2, the method may be performed by an apparatus for performing the method, where the apparatus may be implemented by software and/or hardware, and the method includes:
and S110, detecting local leakage rate data of all leakage components on the containment of the nuclear power plant in response to the current overhaul of the nuclear power plant as the periodical overhaul, and generating a current local leakage rate sum based on the local leakage rate data.
It should be noted that, the overhaul of the nuclear power plant is divided into a first overhaul, a predetermined period overhaul, such as a periodic ten-year overhaul, and a periodic overhaul between the first overhaul and the first predetermined period overhaul, or a periodic overhaul between adjacent predetermined period overhauls; when the primary overhaul and the scheduled-year overhaul are carried out on the nuclear power station, the whole leakage rate of the containment of the nuclear power station is not required to be detected urgently, and the leakage rate of a leakage component on the containment of the nuclear power station is required to be detected, namely the local leakage rate of the containment of the nuclear power station is detected; when the nuclear power station is subjected to regular overhaul, only the leakage rate of a leakage component on the containment of the nuclear power station is detected; among them, the containment vessel of a nuclear power plant is an important facility in the nuclear power plant for preventing radioactive materials from escaping into the environment when a nuclear accident occurs. It is typically a vertical cylindrical hemispherical dome or spherical sealed metal or concrete enclosure that houses most of the systems and equipment of the nuclear steam supply system; various leakage components, such as gates, are mounted on the shell body of the containment vessel of the nuclear power plant, and the leakage components generally have gaps, so that the leakage components have air leakage in an open state or a closed state.
In the implementation, firstly determining which of the first overhaul, the scheduled-year overhaul and the periodic overhaul belongs to the current overhaul of the nuclear power plant, and if the current overhaul of the nuclear power plant is determined to be the periodic overhaul, detecting the leakage rate of the leakage component of the containment vessel of the nuclear power plant only by the current overhaul; specifically, detecting the leakage rate of each leakage component through a preset leak detector, wherein the leakage rate is indicative of the standard flow rate of the leakage gas in the unit time of the corresponding leakage component; obtaining local leakage rate data corresponding to each leakage component one by detecting the leakage rate of each leakage component; further, all detected local leak rate data are added, so that a current local leak rate sum is obtained, and the current local leak rate sum represents the overall leak rate of all leak components on the corresponding nuclear power station.
And S120, acquiring local leakage rate data of the last nuclear power station during overhaul, recording the local leakage rate data as last local leakage rate data, and generating a last local leakage rate sum based on the last local leakage rate data.
It should be noted that, the previous overhaul of the nuclear power plant, which is performed on the current overhaul of the nuclear power plant, is recorded as the last overhaul of the nuclear power plant, which may be one of the first overhaul, the overhaul of the predetermined age and the periodic overhaul, but the local leak rate of the containment vessel of the nuclear power plant is detected by the last overhaul of the nuclear power plant, so as to generate corresponding local leak rate data, which is recorded as the last local leak rate data in this embodiment, and after the last local leak rate data is generated, the last local leak rate data is stored, so as to form corresponding local leak rate history data.
In implementation, after the current local leakage rate sum is generated in step S110, further, corresponding last local leakage rate data is obtained from the pre-stored local leakage rate history data, where the last local leakage rate data is the local leakage rate data of each leakage component detected when the nuclear power station was overhauled last time; further, all the acquired last local leak rate data are added, so that the sum of the last local leak rates is obtained.
S130, generating a local leakage rate sum difference value based on the current local leakage rate sum and the last local leakage rate sum.
It should be noted that, after the current local leakage rate sum is generated in step S110 and the last local leakage rate sum is generated in step S120, a difference between the current local leakage rate sum and the last local leakage rate sum may be calculated, so as to obtain a local leakage rate sum difference; the difference value of the total local leakage rate represents the leakage rate of all leakage components of the containment of the nuclear power plant during the current overhaul of the nuclear power plant relative to the previous overhaul of the nuclear power plant, namely the increase of the total local leakage rate during the adjacent two overhaul of the nuclear power plant; the leakage condition of the containment vessel of the nuclear power plant is basically caused by leakage components, so that the total difference of local leakage rates, namely the increment of the overall leakage rate of the containment vessel of the nuclear power plant during the overhaul of the adjacent two nuclear power plants, is calculated, and under the condition that the total difference of the local leakage rates is calculated, the overall leakage rate of the containment vessel detected during the overhaul of the nuclear power plant last time is known, and then the overall leakage rate of the containment vessel of the current nuclear power plant, namely the overall leakage rate of the containment vessel of the nuclear power plant during the overhaul of the current time, can be calculated.
In implementation, after the current local leakage rate sum is generated in step S110 and the last local leakage rate sum is generated in step S120, further, a difference between the current local leakage rate sum and the last local leakage rate sum is calculated, so as to obtain a corresponding local leakage rate sum difference.
S140, acquiring the integral leakage rate of the containment during the overhaul of the last nuclear power station, and recording the integral leakage rate of the containment as the integral leakage rate of the last time; the current containment overall leak rate is generated based on the local leak rate sum difference and the last containment overall leak rate.
If the total leak rate of the containment vessel at the time of the last overhaul of the nuclear power plant is further obtained, the current total leak rate of the containment vessel is calculated according to the calculated total leak rate difference and the total leak rate of the containment vessel at the time of the last overhaul of the nuclear power plant, when the total leak rate difference of the local leak rates is calculated in step S130.
It should be noted that, if the previous overhaul of the nuclear power plant is the first overhaul or the overhaul of a predetermined age, when the previous overhaul of the nuclear power plant is performed, the corresponding integral leakage rate of the containment vessel can be calculated according to a preset integral leakage rate calculation method of the containment vessel; if the last overhaul of the nuclear power plant is a regular overhaul, the corresponding integral leakage rate of the containment can be calculated according to the integral leakage rate calculation method of the current containment introduced in the embodiment; after the integral leak rate of the containment corresponding to the overhaul of the previous nuclear power station is generated, further, the generated integral leak rate of the containment is stored, so that corresponding historical data of the integral leak rate of the containment is obtained.
In the implementation, after the total difference of the local leak rates is calculated in the step S130, further, the integral leak rate of the containment corresponding to the last overhaul of the nuclear power plant is obtained from the stored history data of the integral leak rate of the containment and is recorded as the integral leak rate of the last time; further, the calculated total difference of the local leak rates and the obtained integral leak rate of the last containment are calculated, so that the integral leak rate of the current containment is obtained.
When the current overhaul of the nuclear power plant is a regular overhaul, calculating the sum of the local leakage rate data of all the leakage components to obtain the current local leakage rate sum; then calculating the sum of the local leakage rate data of all the corresponding leakage components during the previous overhaul of the nuclear power station through historical data to obtain the sum of the local leakage rates of the previous time; then calculating the difference value of the sum of the two local leakage rates, namely the difference value of the current local leakage rate sum and the last local leakage rate sum, so as to obtain a difference value of the local leakage rate sum; then, acquiring the integral leakage rate of the containment during the overhaul of the previous nuclear power station through historical data to obtain the integral leakage rate of the containment last time; then calculating the sum of the sum difference value of the integral leakage rate and the local leakage rate of the last containment, thereby obtaining the integral leakage rate of the current containment of the nuclear power station; so in time this nuclear power station is not carried out the detection of the whole leakage rate of containment when repairing again, still can calculate the whole leakage rate of current containment when repairing this time according to local leakage rate sum total difference and the whole leakage rate of last containment, so be convenient for accurately grasp the whole leakproofness condition of nuclear power station containment when repairing at every turn.
In one embodiment, the leakage means comprises one or more of a penetration, a damper, a channel, and an expansion joint; generating a current local leak rate sum based on the local leak rate data, comprising:
s111, acquiring local leakage rate data of the penetrating piece, and recording the local leakage rate data as first local leakage rate data; acquiring local leakage rate data of the air gate, and recording the local leakage rate data as second local leakage rate data; acquiring local leakage rate data of a channel, and recording the local leakage rate data as third local leakage rate data; local leakage rate data of the expansion joint is obtained and recorded as fourth local leakage rate data.
In one embodiment, the leakage means includes one or more of a penetration, an air gate, a passage, and an expansion joint; in this embodiment, the types of the leakage members include, in particular, a penetration, a damper, a passage, and an expansion joint, and the number of each leakage member is at least one.
In practice, detecting local leak rate data for each leak component using a leak detector, thereby obtaining local leak rate data for each leak component in a one-to-one correspondence; specifically, the leak detector is used for detecting the local leak rate data of each penetrating piece to obtain first local leak rate data, the leak detector is used for detecting the local leak rate data of each air lock gate to obtain second local leak rate data, the leak detector is used for detecting the local leak rate data of each channel to obtain third local leak rate data, and the leak detector is used for detecting the local leak rate data of each expansion joint to obtain fourth local leak rate data.
S112, calculating the sum value of the first partial leakage rate data, the second partial leakage rate data, the third partial leakage rate data and the fourth partial leakage rate data to obtain the current partial leakage rate sum.
Through implementation of the step S111, first local leakage rate data corresponding to each penetrating piece one by one, first local leakage rate data corresponding to each air lock gate one by one, first local leakage rate data corresponding to each channel one by one, and first local leakage rate data corresponding to each expansion joint one by one can be obtained; further, all the first partial leak rate data, all the second partial leak rate data, all the third partial leak rate data, and all the fourth partial leak rate data are added to obtain a sum value of all the partial leak rate data, which is recorded as a current partial leak rate sum.
In one embodiment, generating the local leak rate sum difference based on the current local leak rate sum and the last local leak rate sum includes:
s131, calculating the difference between the current local leakage rate sum and the last local leakage rate sum, and recording the difference as an initial leakage rate sum difference.
It should be noted that, the current local leakage rate sum may be calculated based on the local leakage rate data of each leakage component, the corresponding last local leakage rate data may be obtained based on the local leakage rate history data, and then all the obtained last local leakage rate data may be summed to obtain the last local leakage rate sum; the difference between the current local leakage rate sum and the last local leakage rate sum, namely the initial leakage rate sum difference, can be calculated.
In an implementation, after the current local leakage rate sum and the last local leakage rate sum are calculated, further, a difference between the current local leakage rate sum and the last local leakage rate sum is calculated, so as to obtain an initial leakage rate sum difference. Illustratively, assuming that the current local leak rate sum is 1.5slm and the last local leak rate sum is 1.4slm, the corresponding initial leak rate sum difference is 1.5slm-1.4slm = 0.1slm.
S132, processing the initial leakage rate sum difference value based on a preset unit conversion formula to obtain a local leakage rate sum difference value.
It should be noted that, the unit of the sum difference of the initial leakage rates is slm, which belongs to the flow unit; adding the sum of the difference value of the initial leakage rate and the integral leakage rate of the last containment, so as to calculate the integral leakage rate of the current containment, wherein the integral leakage rate of the last containment is 0.1 percent/day of the total mass of containment air, and belongs to a percentage unit; obviously, the units of the two are not unified, and therefore, a preset unit conversion formula is needed to convert the unit of the initial leakage rate sum difference value, so that the unit of the initial leakage rate sum difference value and the unit of the last integral leakage rate of the containment are unified.
In the implementation, after the initial leakage rate sum difference value and the last integral leakage rate of the containment are obtained, further, the preset unit conversion formula is used for processing the initial leakage rate sum difference value, so that the initial leakage rate sum difference value after unit conversion is obtained and is recorded as the local leakage rate sum difference value.
In one embodiment, the unit conversion formula is:
wherein L is MN Is the sum difference of initial leakage rate, V is the total free volume of the containment and P a Calculating accident peak pressure, P, for containment 0 The pressure is the standard condition pressure; wherein P is a The standard pressure is specifically 101.325kPa.
In one embodiment, generating the current containment overall leak rate based on the local leak rate sum difference and the last containment overall leak rate includes:
s141, obtaining the sum difference value of the local leakage rates and the integral leakage rate of the last containment.
S142, calculating the sum value of the sum difference value of the local leak rates and the integral leak rate of the last containment, and obtaining the integral leak rate of the current containment.
The leakage condition of the containment vessel of the nuclear power plant is basically caused by leakage components, so that the total difference of local leakage rates, namely the increment of the overall leakage rate of the containment vessel of the nuclear power plant during the overhaul of the adjacent two nuclear power plants, is calculated, and under the condition that the total difference of the local leakage rates is calculated, the overall leakage rate of the containment vessel detected during the overhaul of the nuclear power plant last time is known, and then the overall leakage rate of the containment vessel of the current nuclear power plant, namely the overall leakage rate of the containment vessel of the nuclear power plant during the overhaul of the current time, can be calculated.
In the implementation, the calculated total difference value of the local leakage rate is firstly obtained, then the last integral leakage rate of the containment is obtained through the historical data of the integral leakage rate of the containment, and further, the sum value between the total difference value of the local leakage rate and the last integral leakage rate of the containment is calculated, so that the current integral leakage rate of the containment is obtained; for example, assuming a total local leak rate difference of 0.0005 containment air total mass 0.1%/day, the last time the containment overall leak rate was 0.1231 containment air total mass 0.1%/day, the calculated current containment overall leak rate is 0.0005 containment air total mass 0.1%/day+0.1231 containment air total mass 0.1%/day = 0.1236 containment air total mass 0.1%/day.
FIG. 2 is a flow chart of a method of calculating the overall leak rate of a containment vessel in accordance with one embodiment. It should be understood that, although the steps in the flowchart of fig. 2 are shown in sequence as indicated by the arrows, the steps are not necessarily performed in sequence as 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; and at least some of the steps in fig. 2 may include multiple sub-steps or stages that are not necessarily performed at the same time, but may be performed at different times, nor do the order in which the sub-steps or stages are performed necessarily performed in sequence, but may be performed alternately or alternately with at least a portion of the other steps or sub-steps of other steps.
Example two
Based on the same inventive concept, the second embodiment of the present disclosure also provides a current containment overall leak rate calculation device for implementing the above-mentioned related current containment overall leak rate calculation method. The implementation of the solution provided by the device is similar to that described in the above method, so the specific limitations in the embodiments of the present containment overall leak rate calculation device or devices provided below may be referred to above as limitations of the present containment overall leak rate calculation method, and will not be repeated here.
In one embodiment, as shown in FIG. 3, there is provided a current containment overall leak rate calculation apparatus comprising:
and the first leakage rate sum calculation module is used for responding to the current overhaul of the nuclear power plant as the periodical overhaul, detecting local leakage rate data of all leakage components on the containment of the nuclear power plant and generating the current local leakage rate sum based on the local leakage rate data.
And the second leakage rate sum calculation module is used for acquiring the local leakage rate data of the last nuclear power station when the nuclear power station is overhauled, recording the local leakage rate data as the last local leakage rate data, and generating the last local leakage rate sum based on the last local leakage rate data.
And the leakage rate sum difference calculation module is used for generating a local leakage rate sum difference value based on the current local leakage rate sum and the last local leakage rate sum.
The integral leakage rate calculation module is used for obtaining the integral leakage rate of the containment during the overhaul of the nuclear power plant, and recording the integral leakage rate of the containment as the integral leakage rate of the containment last time; the current containment overall leak rate is generated based on the local leak rate sum difference and the last containment overall leak rate.
The various modules in the current containment overall leak rate calculation apparatus described above may be implemented in whole or in part by software, hardware, and combinations 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.
Example III
Fig. 4 is a flowchart of a method for calculating the overall leak rate of a containment, which is provided in the third embodiment of the present application, and referring to fig. 4, the method may be performed by an apparatus for performing the method, and the apparatus may be implemented by software and/or hardware, and the method includes:
and S310, detecting local leakage rate data of all leakage components on the containment of the nuclear power plant in response to the current overhaul of the nuclear power plant as the periodical overhaul, and generating a current local leakage rate sum based on the local leakage rate data.
And S320, acquiring local leakage rate data of the last nuclear power station during overhaul, recording the local leakage rate data as last local leakage rate data, and generating a last local leakage rate sum based on the last local leakage rate data.
S330, generating a local leakage rate sum difference value based on the current local leakage rate sum and the last local leakage rate sum.
S340, acquiring the integral leakage rate of the containment during the overhaul of the last nuclear power station, and recording the integral leakage rate of the containment as the integral leakage rate of the last time; the current containment overall leak rate is generated based on the local leak rate sum difference and the last containment overall leak rate.
It should be noted that, the steps S310-S340 are the same as the steps S110-S140, and detailed descriptions are omitted here.
And S350, in response to the current overhaul of the nuclear power plant not being the periodical overhaul, raising the internal pressure of the containment to a preset pressure.
If the current overhaul of the nuclear power plant is not the regular overhaul, that is, if the current overhaul of the nuclear power plant is the first overhaul or the overhaul of a preset age, the whole leakage rate of the current containment needs to be directly detected;
in practice, when the containment of the nuclear power plant is in a closed state, the air pressure in the containment of the nuclear power plant is increased until the air pressure is detected to reach a predetermined pressure.
S360, acquiring air parameters in the containment, and calculating air quality data in the containment based on the air parameters.
In the implementation, after the air pressure is detected to reach the preset pressure, further, the air pressure in the containment of the nuclear power plant is maintained, and then air parameters, such as air density data, of the air in the containment of the nuclear power plant are collected at regular time; and then calculating the total mass of the air in the containment of the nuclear power station based on the air parameters acquired each time, and then synthesizing the total mass of the air in the containment of the nuclear power station calculated each time, so as to obtain the air quality data in the containment.
S370, approximately fitting the air quality data in the shell to obtain the current integral leakage rate of the containment.
In implementation, after the air quality data in the shell is obtained through S360, further, the air quality data is approximately fitted through a preset approximate fitting model, so that the change rate of the total mass of the air in the containment of the nuclear power station along with time, namely the overall leakage rate of the current containment, is obtained.
FIG. 4 is a flow chart of a method of calculating the overall leak rate of a containment vessel in accordance with one embodiment. It should be understood that, although the steps in the flowchart of fig. 4 are shown in sequence as indicated by the arrows, the steps are not necessarily performed in sequence as 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; and at least some of the steps in fig. 4 may include multiple sub-steps or stages that are not necessarily performed at the same time, but may be performed at different times, nor do the order in which the sub-steps or stages are performed necessarily performed in sequence, but may be performed alternately or alternately with at least a portion of the other steps or sub-steps of other steps.
Example IV
Based on the same inventive concept, the fourth embodiment of the present disclosure also provides a current containment overall leak rate calculation apparatus for implementing the above-mentioned related current containment overall leak rate calculation method. The implementation of the solution provided by the device is similar to that described in the above method, so the specific limitations in the embodiments of the present containment overall leak rate calculation device or devices provided below may be referred to above as limitations of the present containment overall leak rate calculation method, and will not be repeated here.
In one embodiment, as shown in FIG. 5, there is provided a current containment overall leak rate calculation apparatus comprising:
the first leakage rate sum calculation module is used for responding to the fact that the current overhaul of the nuclear power plant is the periodical overhaul, detecting local leakage rate data of all leakage components on the containment of the nuclear power plant, and generating a current local leakage rate sum based on the local leakage rate data;
the second leakage rate sum calculation module is used for acquiring local leakage rate data of the last time of overhaul of the nuclear power station, recording the local leakage rate data as last local leakage rate data, and generating last local leakage rate sum based on the last local leakage rate data;
the leakage rate sum difference calculation module is used for generating a local leakage rate sum difference value based on the current local leakage rate sum and the last local leakage rate sum;
the integral leakage rate calculation module is used for obtaining the integral leakage rate of the containment during the overhaul of the nuclear power plant, and recording the integral leakage rate of the containment as the integral leakage rate of the containment last time; the current containment overall leak rate is generated based on the local leak rate sum difference and the last containment overall leak rate.
The pressure raising module is used for raising the internal pressure of the containment vessel to a preset pressure in response to the fact that the current overhaul of the nuclear power station is not regular overhaul;
the air quality data calculation module is used for acquiring air parameters in the containment vessel and calculating air quality data in the containment vessel based on the air parameters;
and the current leakage rate calculation module is used for approximately fitting the air quality data in the shell to obtain the overall leakage rate of the current containment.
The various modules in the current containment overall leak rate calculation apparatus described above may be implemented in whole or in part by software, hardware, and combinations 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, the internal structure of which may be as shown in fig. 6. The computer device includes a processor, a memory, and a network interface connected by a system bus. Wherein the processor of the computer device is configured to provide computing and control capabilities. The memory of the computer device includes a non-volatile storage medium and an internal memory. The non-volatile storage medium stores an operating system, computer programs, and a database. The internal memory provides an environment for the operation of the operating system and computer programs in the non-volatile storage media. The database of the computer device is used to store XX data. The network interface of the computer device is used for communicating with an external terminal through a network connection. The computer program when executed by a processor implements a current containment overall leak rate calculation method.
Those skilled in the art will appreciate that the architecture shown in fig. 6 is merely a block diagram of a portion of the architecture associated with the disclosed aspects and is not limiting of the computer device to which the disclosed aspects apply, and that a particular computer device may include more or fewer components than shown, or may combine some of the components, or have a different arrangement of components.
In one embodiment, a computer device is provided, comprising a memory and a processor, the memory having stored therein a computer program, the processor implementing the steps of the method embodiments described above when the computer program is executed.
In one embodiment, a computer readable storage medium is provided, as shown in fig. 7, having a computer program stored thereon, which when executed by a processor, implements the steps of the method embodiments described above.
In an embodiment, a computer program product is provided, comprising a computer program which, when executed by a processor, implements the steps of the method embodiments described above.
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 disclosure are information and data authorized by the user or sufficiently authorized by each party.
Those skilled in the art will appreciate that implementing all or part of the above-described methods in accordance with the embodiments 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 by the present disclosure may include at least one of non-volatile and volatile memory, among others. 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), magnetic random access Memory (Magnetoresistive Random Access Memory, MRAM), ferroelectric Memory (Ferroelectric Random Access Memory, FRAM), phase change Memory (Phase ChangeMemory, PCM), graphene Memory, and the like. Volatile memory can include random access memory (RandomAccess Memory, RAM) or external cache memory, and the like. By way of illustration, and not limitation, RAM can be in the form of a variety of forms, such as static random access memory (Static Random Access Memory, SRAM) or dynamic random access memory (Dynamic Random Access Memory, DRAM), and the like. The databases referred to in the various embodiments provided by the present disclosure 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 processors involved in the embodiments provided by the present disclosure may be general-purpose processors, central processing units, graphics processors, digital signal processors, programmable logic, quantum computing-based data processing logic, etc., without limitation 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 merely represent several embodiments of the present disclosure, which are described in more detail and are not to be construed as limiting the scope of the present disclosure. It should be noted that variations and modifications can be made by those skilled in the art without departing from the spirit of the disclosure, which are within the scope of the disclosure. Accordingly, the scope of the present disclosure should be determined from the following claims.
Claims (10)
1. A method for calculating the overall leak rate of a current containment vessel, comprising:
detecting local leakage rate data of all leakage components on a containment of the nuclear power plant in response to the current overhaul of the nuclear power plant being a periodic overhaul, and generating a current local leakage rate sum based on the local leakage rate data;
acquiring local leakage rate data of the last nuclear power station during overhaul, recording the local leakage rate data as last local leakage rate data, and generating a last local leakage rate sum based on the last local leakage rate data;
generating a local leak rate sum difference based on the current local leak rate sum and the last local leak rate sum;
acquiring the integral leakage rate of the containment during the overhaul of the nuclear power plant, and recording the integral leakage rate of the containment as the integral leakage rate of the containment; and generating a current containment overall leak rate based on the local leak rate sum difference and the last containment overall leak rate.
2. A method according to claim 1, wherein the leak component comprises one or more of a penetration, a damper, a passageway, and an expansion joint; the generating a current local leak rate sum based on the local leak rate data includes:
acquiring local leakage rate data of the penetrating piece, and recording the local leakage rate data as first local leakage rate data; acquiring local leakage rate data of the air lock gate valve, and recording the local leakage rate data as second local leakage rate data; acquiring local leakage rate data of the channel, and recording the local leakage rate data as third local leakage rate data; acquiring local leakage rate data of the expansion joint, and recording the local leakage rate data as fourth local leakage rate data;
and calculating the sum value of the first local leakage rate data, the second local leakage rate data, the third local leakage rate data and the fourth local leakage rate data to obtain the current local leakage rate sum.
3. A method according to claim 1, wherein said generating a local leak rate sum difference based on said current local leak rate sum and said last local leak rate sum comprises:
calculating the difference between the current partial leakage rate sum and the last partial leakage rate sum, and recording the difference as an initial leakage rate sum difference;
and processing the initial leakage rate sum difference value based on a preset unit conversion formula to obtain the local leakage rate sum difference value.
4. A method according to claim 3, wherein the unit conversion formula is:
wherein the L is MN Is the sum difference of initial leakage rate, the V is the total free volume of the containment, and the P a Calculating accident peak pressure, said P, for a containment 0 Is the standard pressure.
5. A method according to claim 1, wherein said generating a current overall containment leak rate based on said local leak rate sum difference and said last overall containment leak rate comprises:
acquiring the sum difference value of the local leakage rates and the integral leakage rate of the last containment;
and calculating the sum value of the sum difference value of the local leakage rates and the integral leakage rate of the last containment to obtain the integral leakage rate of the current containment.
6. A method as claimed in claim 1, further comprising:
in response to the current nuclear power plant overhaul not being a periodic overhaul, raising an internal pressure of the containment to a predetermined pressure;
acquiring air parameters in the containment, and calculating air quality data in the containment based on the air parameters;
and approximately fitting the air quality data in the shell to obtain the current integral leakage rate of the containment.
7. A current containment overall leak rate calculation apparatus, the apparatus comprising:
the first leakage rate sum calculation module is used for responding to the current overhaul of the nuclear power plant as the periodic overhaul, detecting local leakage rate data of all leakage components on the containment of the nuclear power plant and generating the current local leakage rate sum based on the local leakage rate data;
the second leakage rate sum calculation module is used for acquiring local leakage rate data of the last nuclear power station when the nuclear power station is overhauled, recording the local leakage rate data as last local leakage rate data, and generating last local leakage rate sum based on the last local leakage rate data;
a leakage rate sum difference calculation module configured to generate a local leakage rate sum difference based on the current local leakage rate sum and the last local leakage rate sum;
the integral leakage rate calculation module is used for obtaining the integral leakage rate of the containment during the overhaul of the nuclear power plant, and recording the integral leakage rate of the containment as the integral leakage rate of the containment last time; and generating a current containment overall leak rate based on the local leak rate sum difference and the last containment overall leak rate.
8. A computer device comprising a memory and a processor, the memory storing a computer program, characterized in that the processor implements the steps of the method of any of claims 1 to 6 when the computer program is executed.
9. A computer readable storage medium, on which a computer program is stored, characterized in that the computer program, when being executed by a processor, implements the steps of the method of any of claims 1 to 6.
10. A computer program product comprising a computer program, characterized in that the computer program, when being executed by a processor, implements the steps of the method of any of claims 1 to 6.
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