CN113487464B - Nuclear power plant accident management method, device, computer equipment and storage medium - Google Patents
Nuclear power plant accident management method, device, computer equipment and storage medium Download PDFInfo
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- 101150010457 SAS5 gene Proteins 0.000 description 2
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- 101100148749 Saccharomyces cerevisiae (strain ATCC 204508 / S288c) SAS2 gene Proteins 0.000 description 1
- 101100148751 Saccharomyces cerevisiae (strain ATCC 204508 / S288c) SAS3 gene Proteins 0.000 description 1
- 101100148755 Saccharomyces cerevisiae (strain ATCC 204508 / S288c) SAS4 gene Proteins 0.000 description 1
- 101100364870 Saccharomyces cerevisiae (strain ATCC 204508 / S288c) SAS5 gene Proteins 0.000 description 1
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Abstract
The application relates to a nuclear power plant accident management method, a device, computer equipment and a storage medium. The method comprises the following steps: obtaining measured parameter data of a nuclear power plant in an accident state; then, at least one accident factor is obtained according to the measured parameter data and a preset accident diagnosis rule; then determining an accident handling sequence according to accident factors and preset accident diagnosis rules; and finally, acquiring an accident mitigation strategy according to the accident handling sequence. By adopting the method, an integrated accident management structure is adopted, the diagnosis flow is simplified, the problems of frequent jump and call in the existing accident handling system are avoided, the emergency response speed is improved, the error risk of staff under high pressure is reduced, and the aim of improving the accident management efficiency of the nuclear power plant can be fulfilled.
Description
Technical Field
The application relates to the technical field of accident handling implementation of nuclear power plants, in particular to a method, a device, computer equipment and a storage medium for managing accidents of a nuclear power plant.
Background
If accident preventive measures of a nuclear power plant fail in the accident development process, accidents will occur, and accident alleviation needs to be implemented. The goal of accident mitigation is to maintain as much of the highly damaged core cooling as possible, achieve a controlled final steady state, and maintain the integrity of the containment as long as possible, thereby gaining more time for off-plant emergency planning. The release of radioactive substances to the outside of the factory is reduced as much as possible, and the long-term pollution of soil and underground water is avoided as much as possible.
The conventional nuclear power plant accident management method has the problems of large workload of technicians and low efficiency of nuclear power plant accident management.
Disclosure of Invention
In view of the foregoing, it is desirable to provide a nuclear power plant incident management method, apparatus, computer device, and storage medium that can improve the efficiency of nuclear power plant incident management.
A method of nuclear power plant incident management, the method comprising:
Obtaining measured parameter data of a nuclear power plant in an accident state;
acquiring at least one accident factor according to the measured parameter data and a preset accident diagnosis rule;
Determining an accident handling sequence according to accident factors and preset accident diagnosis rules;
and acquiring an accident mitigation strategy according to the accident handling sequence.
In one embodiment, the preset accident diagnosis rules are obtained by the following method:
Acquiring parameter data and priority of the parameter data of the nuclear power plant, wherein the parameter data of the nuclear power plant comprises a loop pressure, a reactor cavity water level, a steam generator water level, a loop temperature, a site dosage level, a containment pressure, a containment hydrogen concentration and a containment water level; the priority of the parameter data is from high to low: a loop pressure, a reactor cavity water level, a steam generator water level, a loop temperature, a field dose level, a containment pressure, a containment hydrogen concentration, and a containment water level;
acquiring at least two risk levels, wherein each parameter data at least corresponds to two risk levels;
acquiring a threshold range of each risk level corresponding to each parameter data, wherein each threshold range corresponds to one risk level;
and acquiring a preset accident diagnosis rule according to the threshold range, the risk level, the parameter data and the priority of the parameter data.
In one embodiment, the preset accident diagnosis rules further comprise a risk-free level, and the method further comprises:
If one parameter data is in the threshold range corresponding to the risk-free level, accident factors are not acquired for the parameter data.
In one embodiment, obtaining at least one accident factor according to the measured parameter data and a preset accident diagnosis rule includes:
obtaining comparison results of the measured parameter data and a threshold range of the parameter data in a preset accident diagnosis rule;
and obtaining at most one accident factor according to the comparison result for each measured parameter data.
In one embodiment, determining the order of accident handling based on accident factors and preset accident diagnosis rules comprises:
acquiring the order of the risk levels;
According to the order of the risk levels from high to low, sequencing accident factors according to the priority of the parameter data aiming at each risk level;
and integrating the sequenced accident factors to obtain an accident handling sequence.
In one embodiment, according to an incident handling sequence, obtaining an incident mitigation strategy includes:
acquiring a plurality of management objects according to the accident management targets of the nuclear power plant;
Acquiring a plurality of management elements according to the management objects, wherein each management object corresponds to at least one management element;
acquiring at least one corresponding accident mitigation operation according to each management element;
Merging accident mitigation operations corresponding to each management element to obtain a plurality of accident mitigation strategies;
acquiring the corresponding relation between the accident mitigation strategy and the accident factors;
And acquiring a plurality of accident mitigation strategies one by one according to the accident handling sequence and the corresponding relation.
In one embodiment, the method further comprises:
executing an accident mitigation strategy;
if the measured parameter data is in the threshold range corresponding to the risk-free level and the preset duration is maintained, the accident management monitoring is stopped.
A nuclear power plant incident management apparatus, the apparatus comprising:
The data actual measurement module is used for acquiring actual measurement parameter data of the nuclear power plant in an accident state;
the factor acquisition module is used for acquiring at least one accident factor according to the actually measured parameter data and a preset accident diagnosis rule;
The sequence determining module is used for determining an accident handling sequence according to accident factors and preset accident diagnosis rules;
and the strategy generation module is used for acquiring the accident mitigation strategy according to the accident handling sequence.
A computer device comprising a memory storing a computer program and a processor which when executing the computer program performs the steps of:
Obtaining measured parameter data of a nuclear power plant in an accident state;
acquiring at least one accident factor according to the measured parameter data and a preset accident diagnosis rule;
Determining an accident handling sequence according to accident factors and preset accident diagnosis rules;
and acquiring an accident mitigation strategy according to the accident handling sequence.
A computer readable storage medium having stored thereon a computer program which when executed by a processor performs the steps of:
Obtaining measured parameter data of a nuclear power plant in an accident state;
acquiring at least one accident factor according to the measured parameter data and a preset accident diagnosis rule;
Determining an accident handling sequence according to accident factors and preset accident diagnosis rules;
and acquiring an accident mitigation strategy according to the accident handling sequence.
According to the nuclear power plant accident management method, the device, the computer equipment and the storage medium, the actual measurement parameter data of the nuclear power plant in an accident state are obtained; then, at least one accident factor is obtained according to the measured parameter data and a preset accident diagnosis rule; then determining an accident handling sequence according to accident factors and preset accident diagnosis rules; and finally, acquiring an accident mitigation strategy according to the accident handling sequence. Through the integrated accident management structure, the diagnosis flow is simplified, the problems of frequent jump and call in the existing accident handling system are avoided, the emergency response speed is improved, the error risk of workers under high pressure is reduced, and the aim of improving the accident management efficiency of the nuclear power plant can be fulfilled.
Drawings
FIG. 1 is a flow diagram of a method of accident management in a nuclear power plant in one embodiment;
FIG. 2 is a flow chart of a method for obtaining preset incident diagnosis rules in one embodiment;
FIG. 3 is a schematic diagram of a preset incident diagnosis rule table in one embodiment;
FIG. 4 is a schematic diagram of an accident handling sequence in another embodiment;
FIG. 5 is a block diagram of a nuclear power plant incident management apparatus in one embodiment;
Fig. 6 is an internal structural diagram of a computer device in one embodiment.
Detailed Description
The present application will be described in further detail with reference to the drawings and examples, in order to make the objects, technical solutions and advantages of the present application more apparent. It should be understood that the specific embodiments described herein are for purposes of illustration only and are not intended to limit the scope of the application.
In one embodiment, as shown in fig. 1, a nuclear power plant accident management method is provided, where the method is applied to a terminal to illustrate the accident, it is understood that the method may also be applied to a server, and may also be applied to a system including the terminal and the server, and implemented through interaction between the terminal and the server. In this embodiment, the method includes the steps of:
And 102, acquiring actual measurement parameter data of the nuclear power plant in an accident state.
The accident of the nuclear power plant is generally divided into design reference accident and serious accident, and the method is mainly used for treating the serious accident. Serious accidents are accidents that the reactor core of a nuclear power plant is seriously damaged, and the integrity of a containment is possibly damaged, so that environmental radioactive pollution and personal casualties are caused, and huge losses are generated. The existing nuclear power plant is based on the deep defense principle, is provided with a plurality of barriers and special safety facilities, adopts strict quality management and operator selection training system, and has strict requirements on site selection of the nuclear power plant, so that the nuclear power plant has strong capability of resisting external disasters and internal events. Serious accidents can be caused only when multiple faults and misoperation occur continuously. In contrast to the design benchmark incidents of a nuclear power plant that only consider single faults as a characteristic, severe incidents are generally incidents that are superimposed by multiple faults and ultimately lead to damage to the core. The probability of occurrence of a serious accident is low but not impossible.
Specifically, the actual measurement parameter data of the nuclear power plant in the accident state is obtained through the monitoring terminal of the nuclear power plant, and the types of the actual measurement parameter data can include loop pressure, reactor cavity water level, steam generator water level, loop temperature, site dosage level, containment pressure, containment hydrogen concentration, containment water level and the like.
Step 104, obtaining at least one accident factor according to the measured parameter data and a preset accident diagnosis rule.
The accident factor refers to the reason for causing the accident of the current nuclear power plant, and is specifically embodied in the condition that one or more parameter data are out of a normal range.
Specifically, a plurality of threshold ranges are configured for each parameter data in a preset accident diagnosis rule, measured parameter data which is not in a normal threshold range can be obtained by comparing measured parameter data with the plurality of threshold ranges, and accident factors can be determined according to the measured parameter data, and in general, one measured parameter data corresponds to one accident factor.
And 106, determining an accident handling sequence according to the accident factors and preset accident diagnosis rules.
The accident handling sequence refers to the handling sequence of accident factors.
Specifically, dimensions such as the influence range of the release of accident factors from fission products, threat degree of containment integrity, decay heat export scheme, long-term stability and controllability of the power plant state and the like can be assessed in a preset accident diagnosis rule, so that the risk grade of the accident factors can be obtained, and the accidents caused by the accident factors with higher risks are preferentially treated. If a plurality of accident factors exist, each accident factor is processed according to the risk level from high to low. The preset accident diagnosis rules also carry out priority allocation on the parameter data of the nuclear power plant, and because the reasons, positions and solutions of the accidents corresponding to each parameter data are different, accident factors related to the parameter data with high priority are preferentially processed under the same risk level.
And step 108, acquiring an accident mitigation strategy according to the accident handling sequence.
The accident mitigation strategy is an operation and action required by a pointer to an out-of-limit accident factor and solving the out-of-limit accident factor, and the operation and action are called accident mitigation operation. One accident mitigation strategy typically includes a plurality of accident mitigation operations.
Specifically, in general, an accident mitigation strategy corresponds to an accident factor. When a plurality of accident factors exceed the limit, the accident mitigation strategies are acquired one by one according to the accident handling sequence.
In the nuclear power plant accident management method, the actual measurement parameter data of the nuclear power plant in an accident state is obtained; then, at least one accident factor is obtained according to the measured parameter data and a preset accident diagnosis rule; then determining an accident handling sequence according to accident factors and preset accident diagnosis rules; and finally, acquiring an accident mitigation strategy according to the accident handling sequence. Through the integrated accident management structure, the diagnosis flow is simplified, the problems of frequent jump and call in the existing accident handling system are avoided, the emergency response speed is improved, the error risk of workers under high pressure is reduced, and the aim of improving the accident management efficiency of the nuclear power plant can be fulfilled.
In one embodiment, as shown in fig. 2, the preset incident diagnosis rules are obtained by the following method:
Step 202, acquiring parameter data and priority of the parameter data of a nuclear power plant, wherein the parameter data of the nuclear power plant comprises a loop pressure, a reactor cavity water level, a steam generator water level, a loop temperature, a site dosage level, a containment pressure, a containment hydrogen concentration and a containment water level; the priority of the parameter data is from high to low: a loop pressure, a reactor cavity water level, a steam generator water level, a loop temperature, a field dose level, a containment pressure, a containment hydrogen concentration, and a containment water level.
Specifically, the parameter data of the nuclear power plant is obtained, then the parameter data are prioritized, the parameter data with the highest priority are ranked before the parameter data with the highest priority, which means that the accident factors related to the parameter data have the highest alleviation priority. The priorities of the parameter data are respectively as follows from top to bottom: a loop pressure, a reactor cavity water level, a steam generator water level, a loop temperature, a field dose level, a containment pressure, a containment hydrogen concentration, and a containment water level.
In step 204, at least two risk levels are obtained, and each parameter data corresponds to at least two risk levels.
Specifically, a plurality of risk levels are set for each parameter data, and the number of risk levels for each parameter data may be different. For example, some parameter data may set four risk levels of high risk, medium risk, low risk, and no risk, and some parameter data may set only two risk levels of high risk and no risk. The specific risk level setting mode is determined according to the actual condition of the nuclear power plant.
In step 206, a threshold range corresponding to each parameter data is obtained for each risk level, and each threshold range corresponds to one risk level.
Specifically, a threshold range is set for each risk level corresponding to each parameter data. If the measured value of a certain measured parameter data is within a threshold range of a risk level, the measured parameter data is judged to be in the risk level.
Step 208, obtaining a preset accident diagnosis rule according to the threshold range, the risk level, the parameter data and the priority of the parameter data.
Specifically, the preset accident diagnosis rule can be obtained by integrating the threshold range, the risk level, the parameter data and the priority of the parameter data. In actual use, the preset accident diagnosis rules can be embodied in a tabular manner. For example, as shown in the preset accident diagnosis rule table of fig. 3, the first column is set to the parameter data (a loop pressure, a reactor cavity water level, a steam generator water level, a loop temperature, a field dose level, a containment pressure, a containment hydrogen concentration, and a containment water level) arranged from top to bottom according to the priority, the first row is set to the risk level (risk level 1, risk level 2, risk level 3, risk level 4) arranged from top to bottom according to the risk from top to bottom, one cell filled with the threshold range reflects the threshold range of the risk level of the column corresponding to the parameter data of the row, and the empty cell indicates that the parameter data of the row does not set the risk level of the column. The risk level can be selected from red, orange, yellow and green from high to low for marking, so that the high risk level is more visual and striking.
In this embodiment, parameter data of a nuclear power plant and priority of the parameter data are obtained; then, acquiring at least two risk levels, wherein each parameter data at least corresponds to two risk levels; further acquiring a threshold range of each risk level corresponding to each parameter data, wherein each threshold range corresponds to one risk level; and finally, acquiring a preset accident diagnosis rule according to the threshold range, the risk level, the parameter data and the priority of the parameter data. By using the preset accident diagnosis rules to treat the nuclear power plant accidents, the diagnosis process is simplified, the problems of frequent jump and call in the current accident treatment system are avoided, the emergency response speed is improved, the error risk of workers under high pressure is reduced, and the aim of improving the accident management efficiency of the nuclear power plant can be fulfilled.
In one embodiment, the preset accident diagnosis rules further comprise a risk-free level, and the method further comprises: if one parameter data is in the threshold range corresponding to the risk-free level, accident factors are not acquired for the parameter data.
Specifically, a threshold range corresponding to a risk-free level is a normal range of the parameter data. Next, for example, as shown in fig. 3, the preset accident diagnosis rule is shown in table, the risk level 4 in the fourth column is no risk level, and if the parameter data is within the threshold range of the risk level 4, no accident factor is obtained for the parameter data.
In one embodiment, obtaining at least one accident factor according to the measured parameter data and the preset accident diagnosis rules includes: obtaining comparison results of the measured parameter data and a threshold range of the parameter data in a preset accident diagnosis rule; and obtaining at most one accident factor according to the comparison result for each measured parameter data.
Specifically, after the actually measured parameter data are obtained, each actually measured parameter data are respectively compared with a threshold range of the parameter data in a preset accident diagnosis rule. If one measured parameter data is not in the normal range, acquiring accident factors from the measured parameter data, wherein the accident factors can be directly expressed as the current value of the measured parameter data; if one measured parameter data is in the normal range, accident factors are not acquired for the measured parameter data. Thus, when one parameter data is in the normal range, the parameter data corresponds to 0 accident factors, and when one parameter data is not in the normal range, the parameter data corresponds to 1 accident factor.
In one embodiment, determining an incident treatment order based on incident factors and preset incident diagnostic rules comprises: acquiring the order of the risk levels; according to the order of the risk levels from high to low, sequencing accident factors according to the priority of the parameter data aiming at each risk level; and integrating the sequenced accident factors to obtain an accident handling sequence.
Specifically, the order of the risk level and the order of the priority of the parameter data are determined first. And acquiring all accident factors in the highest risk level, and sequencing the accident factors in the highest risk level according to the priority of the parameter data, wherein the accident factors corresponding to the parameter data with high priority are ranked in front. And then, similarly, acquiring all accident factors in the second high risk level, and sequencing the accident factors in the second high risk level according to the priority of the parameter data. And sequencing the accident factors in the lowest risk level according to the priority of the parameter data until all the accident factors in the lowest risk level are acquired. Accident factors of low risk level are ranked behind accident factors of high risk level. In the above example, when the preset accident diagnosis rule table shown in fig. 3 is adopted, the accident handling sequence is as shown in fig. 4, and the sequence is ordered from top to bottom from the first column.
In this embodiment, the order of the risk level is obtained; then, according to the order of the risk levels from high to low, sequencing accident factors according to the priority of the parameter data aiming at each risk level; and finally integrating the sequenced accident factors to obtain an accident handling sequence. By using the accident handling sequence to process the accidents of the nuclear power plant, the high-risk accidents are preferentially processed, the problems of frequent jump and call in the existing accident handling system are avoided, the error risk of workers under high pressure is reduced, and the aim of improving the accident management efficiency of the nuclear power plant can be fulfilled.
In one embodiment, according to an incident handling order, obtaining an incident mitigation strategy includes: acquiring a plurality of management objects according to the accident management targets of the nuclear power plant; acquiring a plurality of management elements according to management objects, wherein each management object corresponds to at least one management element; acquiring at least one corresponding accident mitigation operation according to each management element; merging accident relieving operation corresponding to each management element to obtain a plurality of accident relieving strategies; acquiring a corresponding relation between an accident mitigation strategy and accident factors; and acquiring a plurality of accident mitigation strategies one by one according to the accident handling sequence and the corresponding relation.
Specifically, the accident management goal of a nuclear power plant refers to certain conditions that the nuclear power plant needs to reach. For example, decay heat derivation, containment barrier integrity, radioactivity control, etc., are management goals, as shown in table 1 below. At least one management object may be determined from each nuclear power plant incident management objective, for example, two management objects may be determined from decay heat derivation: the reactor core state is controllable and stable, and the spent fuel state is controllable and stable. And then respectively determining at least one management element of each management object, and formulating corresponding accident mitigation operations according to each management element, wherein each management element can correspond to a plurality of accident mitigation operations to cope with.
TABLE 1
Further, the accident mitigation operations corresponding to each accident factor are integrated and merged, and a plurality of accident mitigation strategies are obtained. And then according to what accident factors can be specifically solved by the accident relief strategy, obtaining the corresponding relation between the accident relief strategy and the accident factors, wherein in general, the accident factors with different risk levels corresponding to one parameter data can adopt one accident relief strategy. Finally, the accident mitigation strategies are acquired one by one according to the accident handling sequence, and the accident mitigation strategies are prepared to be executed in sequence.
For example, when a preset accident diagnosis rule table as shown in fig. 3 is adopted, an accident mitigation strategy may be configured for each parameter data, and each accident mitigation strategy is respectively indicated as SAS1, SAS2, SAS3, SAS4, SAS5, SAS6, SAS7 and SAS8, and corresponds to a loop pressure, a reactor cavity water level, a steam generator water level, a loop temperature, a field dose level, a containment pressure, a containment hydrogen concentration and a containment water level, respectively. SAS-5 (risk level 1) →sas-6 (risk level 1) →sas-7 (risk level 1) →sas-1 (risk level 2) →sas-2 (risk level 2) →sas-3 (risk level 2) →sas-4 (risk level 2) →sas-5 (risk level 2) →sas-6 (risk level 2) →sas-7 (risk level 2) →sas-1 (risk level 3) →sas-2 (risk level 3) →sas-3 (risk level 3) →sas-6 (risk level 3) →sas-7 (risk level 3), no accident mitigation policy is required since the risk level 4 is a no-risk level, no accident factor exists. In the actual implementation process, each parameter data of the nuclear power plant is a determined value (such as containment pressure), so that each measured parameter data can only fall into one risk level, and therefore, one accident mitigation strategy can only be used once in one accident management process, and the problem of repeated use of the same accident mitigation strategy in two accident management logics at present is avoided.
In one embodiment, the above nuclear power plant accident management method further includes: executing an accident mitigation strategy; if the measured parameter data is in the threshold range corresponding to the risk-free level and the preset duration is maintained, the accident management monitoring is stopped.
The accident management monitoring refers to a process from obtaining actual measurement parameter data of the nuclear power plant in an accident state to obtaining at least one accident factor according to the actual measurement parameter data and a preset accident diagnosis rule.
Specifically, a plurality of accident mitigation strategies are executed according to the accident handling order, or an accident management guideline is generated according to the accident handling order and the plurality of accident mitigation strategies, and then the accident management guideline is executed. If all the measured parameter data are in the threshold range corresponding to the risk-free level and the preset duration is maintained, the accident management monitoring is stopped. For example, the reactor core/spent fuel pool and the containment state are stable and controllable for a long time (such as 24 hours or 72 hours), and are expected to be kept continuously, at the moment, all parameter data are in a normal range, each parameter data is in a risk-free level, the number of acquired accident factors is 0, and the accident management monitoring is stopped.
It should be understood that, although the steps in the flowcharts of fig. 1-2 are shown in order as indicated by the arrows, these steps are not necessarily performed in order 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. Moreover, at least some of the steps in fig. 1-2 may include multiple 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 steps or stages are performed necessarily performed in sequence, but may be performed alternately or alternately with at least a portion of the steps or stages in other steps or other steps.
In one embodiment, as shown in fig. 5, there is provided a nuclear power plant incident management apparatus 500, comprising: a data measurement module 501, a factor acquisition module 502, a sequence determination module 503 and a policy generation module 504,
Wherein:
The data actual measurement module 501 is configured to obtain actual measurement parameter data of the nuclear power plant in an accident state.
The factor obtaining module 502 is configured to obtain at least one accident factor according to the measured parameter data and a preset accident diagnosis rule. The preset accident diagnosis rule further comprises a risk-free level, and if one parameter data is in a threshold range corresponding to the risk-free level, accident factors are not acquired for the parameter data.
A sequence determining module 503, configured to determine an accident handling sequence according to the accident factor and a preset accident diagnosis rule.
The policy generation module 504 is configured to obtain an accident mitigation policy according to the accident handling sequence.
In one embodiment, the apparatus further comprises:
The parameter data acquisition module is used for acquiring parameter data of the nuclear power plant and priority of the parameter data, wherein the parameter data of the nuclear power plant comprises loop pressure, reactor cavity water level, steam generator water level, loop temperature, site dosage level, containment pressure, containment hydrogen concentration and containment water level; the priority of the parameter data is from high to low: a loop pressure, a reactor cavity water level, a steam generator water level, a loop temperature, a field dose level, a containment pressure, a containment hydrogen concentration, and a containment water level.
The risk level acquisition module is used for acquiring at least two risk levels, and each parameter data at least corresponds to two risk levels.
The threshold range obtaining module is configured to obtain a threshold range of each risk level corresponding to each parameter data, where each threshold range corresponds to one risk level.
The diagnosis rule acquisition module is used for acquiring a preset accident diagnosis rule according to the threshold range, the risk level, the parameter data and the priority of the parameter data.
In one embodiment, the factor obtaining module 502 is further configured to obtain a comparison result between the measured parameter data and a threshold range of parameter data in a preset accident diagnosis rule; and obtaining at most one accident factor according to the comparison result for each measured parameter data.
In one embodiment, the order determining module 503 is further configured to obtain a high-low order of the risk level; according to the order of the risk levels from high to low, sequencing accident factors according to the priority of the parameter data aiming at each risk level; and integrating the sequenced accident factors to obtain an accident handling sequence.
In one embodiment, the policy generation module 504 is further configured to obtain a plurality of management objects according to the nuclear power plant incident management objective; acquiring a plurality of management elements according to the management objects, wherein each management object corresponds to at least one management element; acquiring at least one corresponding accident mitigation operation according to each management element; merging accident mitigation operations corresponding to each management element to obtain a plurality of accident mitigation strategies; acquiring the corresponding relation between the accident mitigation strategy and the accident factors; and acquiring a plurality of accident mitigation strategies one by one according to the accident handling sequence and the corresponding relation.
In one embodiment, the apparatus further comprises:
the strategy execution module is used for executing the accident mitigation strategy; if the measured parameter data is in the threshold range corresponding to the risk-free level and the preset duration is maintained, the accident management monitoring is stopped.
The specific limitation regarding the accident management apparatus of the nuclear power plant may be referred to as the limitation regarding the accident management method of the nuclear power plant hereinabove, and will not be described herein. The above-mentioned various modules in the accident management apparatus of the nuclear power plant may be implemented in whole or in part by software, hardware, and a combination thereof. The above modules may be embedded in hardware or may be independent of a processor in the computer device, or may be stored in software in a memory in the computer device, so that the processor may call and execute operations corresponding to the above modules.
In one embodiment, a computer device is provided, which may be a terminal, and the internal structure of which may be as shown in fig. 6. The computer device includes a processor, a memory, a communication interface, a display screen, and an input device 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 and a computer program. The internal memory provides an environment for the operation of the operating system and computer programs in the non-volatile storage media. The communication interface of the computer device is used for carrying out wired or wireless communication with an external terminal, and the wireless mode can be realized through WIFI, an operator network, NFC (near field communication) or other technologies. The computer program when executed by a processor implements a method for managing nuclear power plant incidents. The display screen of the computer equipment can be a liquid crystal display screen or an electronic ink display screen, and the input device of the computer equipment can be a touch layer covered on the display screen, can also be keys, a track ball or a touch pad arranged on the shell of the computer equipment, and can also be an external keyboard, a touch pad or a mouse and the like.
It will be appreciated by those skilled in the art that the structure shown in FIG. 6 is merely a block diagram of some of the structures associated with the present inventive arrangements and is not limiting of the computer device to which the present inventive arrangements may be applied, and that a particular computer device may include more or fewer components than shown, or may combine some of the components, or have a different arrangement of components.
In one embodiment, a computer device is provided comprising a memory and a processor, the memory having stored therein a computer program, the processor when executing the computer program performing the steps of:
Obtaining measured parameter data of a nuclear power plant in an accident state;
acquiring at least one accident factor according to the measured parameter data and a preset accident diagnosis rule;
Determining an accident handling sequence according to accident factors and preset accident diagnosis rules;
and acquiring an accident mitigation strategy according to the accident handling sequence.
In one embodiment, the processor when executing the computer program further performs the steps of:
Acquiring parameter data and priority of the parameter data of the nuclear power plant, wherein the parameter data of the nuclear power plant comprises a loop pressure, a reactor cavity water level, a steam generator water level, a loop temperature, a site dosage level, a containment pressure, a containment hydrogen concentration and a containment water level; the priority of the parameter data is from high to low: a loop pressure, a reactor cavity water level, a steam generator water level, a loop temperature, a field dose level, a containment pressure, a containment hydrogen concentration, and a containment water level;
acquiring at least two risk levels, wherein each parameter data at least corresponds to two risk levels;
acquiring a threshold range of each risk level corresponding to each parameter data, wherein each threshold range corresponds to one risk level;
and acquiring a preset accident diagnosis rule according to the threshold range, the risk level, the parameter data and the priority of the parameter data.
In one embodiment, the processor when executing the computer program further performs the steps of:
The preset accident diagnosis rule further comprises a risk-free level, and if one parameter data is in a threshold range corresponding to the risk-free level, accident factors are not acquired for the parameter data.
In one embodiment, the processor when executing the computer program further performs the steps of:
obtaining comparison results of the measured parameter data and a threshold range of the parameter data in a preset accident diagnosis rule;
and obtaining at most one accident factor according to the comparison result for each measured parameter data.
In one embodiment, the processor when executing the computer program further performs the steps of:
acquiring the order of the risk levels;
According to the order of the risk levels from high to low, sequencing accident factors according to the priority of the parameter data aiming at each risk level;
and integrating the sequenced accident factors to obtain an accident handling sequence.
In one embodiment, the processor when executing the computer program further performs the steps of:
acquiring a plurality of management objects according to the accident management targets of the nuclear power plant;
Acquiring a plurality of management elements according to the management objects, wherein each management object corresponds to at least one management element;
acquiring at least one corresponding accident mitigation operation according to each management element;
Merging accident mitigation operations corresponding to each management element to obtain a plurality of accident mitigation strategies;
acquiring the corresponding relation between the accident mitigation strategy and the accident factors;
And acquiring a plurality of accident mitigation strategies one by one according to the accident handling sequence and the corresponding relation.
In one embodiment, the processor when executing the computer program further performs the steps of:
executing an accident mitigation strategy;
if the measured parameter data is in the threshold range corresponding to the risk-free level and the preset duration is maintained, the accident management monitoring is stopped.
In one embodiment, a computer readable storage medium is provided having a computer program stored thereon, which when executed by a processor, performs the steps of:
Obtaining measured parameter data of a nuclear power plant in an accident state;
acquiring at least one accident factor according to the measured parameter data and a preset accident diagnosis rule;
Determining an accident handling sequence according to accident factors and preset accident diagnosis rules;
and acquiring an accident mitigation strategy according to the accident handling sequence.
In one embodiment, the computer program when executed by the processor further performs the steps of:
Acquiring parameter data and priority of the parameter data of the nuclear power plant, wherein the parameter data of the nuclear power plant comprises a loop pressure, a reactor cavity water level, a steam generator water level, a loop temperature, a site dosage level, a containment pressure, a containment hydrogen concentration and a containment water level; the priority of the parameter data is from high to low: a loop pressure, a reactor cavity water level, a steam generator water level, a loop temperature, a field dose level, a containment pressure, a containment hydrogen concentration, and a containment water level;
acquiring at least two risk levels, wherein each parameter data at least corresponds to two risk levels;
acquiring a threshold range of each risk level corresponding to each parameter data, wherein each threshold range corresponds to one risk level;
and acquiring a preset accident diagnosis rule according to the threshold range, the risk level, the parameter data and the priority of the parameter data.
In one embodiment, the computer program when executed by the processor further performs the steps of:
The preset accident diagnosis rule further comprises a risk-free level, and if one parameter data is in a threshold range corresponding to the risk-free level, accident factors are not acquired for the parameter data.
In one embodiment, the computer program when executed by the processor further performs the steps of:
obtaining comparison results of the measured parameter data and a threshold range of the parameter data in a preset accident diagnosis rule;
and obtaining at most one accident factor according to the comparison result for each measured parameter data.
In one embodiment, the computer program when executed by the processor further performs the steps of:
acquiring the order of the risk levels;
According to the order of the risk levels from high to low, sequencing accident factors according to the priority of the parameter data aiming at each risk level;
and integrating the sequenced accident factors to obtain an accident handling sequence.
In one embodiment, the computer program when executed by the processor further performs the steps of:
acquiring a plurality of management objects according to the accident management targets of the nuclear power plant;
Acquiring a plurality of management elements according to the management objects, wherein each management object corresponds to at least one management element;
acquiring at least one corresponding accident mitigation operation according to each management element;
Merging accident mitigation operations corresponding to each management element to obtain a plurality of accident mitigation strategies;
acquiring the corresponding relation between the accident mitigation strategy and the accident factors;
And acquiring a plurality of accident mitigation strategies one by one according to the accident handling sequence and the corresponding relation.
In one embodiment, the computer program when executed by the processor further performs the steps of:
executing an accident mitigation strategy;
if the measured parameter data is in the threshold range corresponding to the risk-free level and the preset duration is maintained, the accident management monitoring is stopped.
Those skilled in the art will appreciate that implementing all or part of the above described methods may be accomplished by way of a computer program stored on a non-transitory computer readable storage medium, which when executed, may comprise the steps of the embodiments of the methods described above. Any reference to memory, storage, database, or other medium used in embodiments provided herein may include at least one of non-volatile and volatile memory. The nonvolatile Memory may include Read-Only Memory (ROM), magnetic tape, floppy disk, flash Memory, optical Memory, or the like. Volatile memory can include random access memory (Random Access Memory, RAM) or external cache memory. By way of illustration, and not limitation, RAM can be in various forms such as static random access memory (Static Random Access Memory, SRAM) or dynamic random access memory (Dynamic Random Access Memory, DRAM), etc.
The 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 above examples illustrate only a few embodiments of the application, which are described in detail and are not to be construed as limiting the scope of the application. It should be noted that it will be apparent to those skilled in the art that several variations and modifications can be made without departing from the spirit of the application, which are all within the scope of the application. Accordingly, the scope of protection of the present application is to be determined by the appended claims.
Claims (10)
1. A method for managing an accident in a nuclear power plant, the method comprising:
Obtaining measured parameter data of a nuclear power plant in an accident state;
acquiring at least one accident factor according to the measured parameter data and a preset accident diagnosis rule;
determining an accident processing sequence according to the risk level of at least one accident factor in the preset accident diagnosis rule and the priority of different parameter data under the same risk level;
Acquiring an accident mitigation strategy according to the accident handling sequence;
The preset accident diagnosis rules are obtained through the following steps:
Acquiring parameter data and priority of the parameter data of a nuclear power plant, wherein the parameter data of the nuclear power plant comprises a loop pressure, a reactor cavity water level, a steam generator water level, a loop temperature, a site dosage level, a containment pressure, a containment hydrogen concentration and a containment water level; the priority of the parameter data is from high to low: a loop pressure, a reactor cavity water level, a steam generator water level, a loop temperature, a field dose level, a containment pressure, a containment hydrogen concentration, and a containment water level; acquiring at least two risk levels, wherein each parameter data at least corresponds to two risk levels; acquiring a threshold range of each risk level corresponding to each parameter data, wherein each threshold range corresponds to one risk level; acquiring the preset accident diagnosis rule according to the threshold range, the risk level, the parameter data and the priority of the parameter data;
wherein, according to the accident handling sequence, the obtaining the accident mitigation strategy includes:
Acquiring a plurality of management objects according to the accident management targets of the nuclear power plant; acquiring a plurality of management elements according to the management objects, wherein each management object corresponds to at least one management element; acquiring at least one corresponding accident mitigation operation according to each management element; merging accident mitigation operations corresponding to each management element to obtain a plurality of accident mitigation strategies; acquiring the corresponding relation between the accident mitigation strategy and the accident factors; acquiring a plurality of accident mitigation strategies one by one according to the accident handling sequence and the corresponding relation;
Wherein the management objective includes at least one of decay heat derivation, containment barrier integrity and radioactivity control; the decay heat leading-out corresponding management object comprises at least one of reactor core state controllable stability and spent fuel state controllable stability; the management object which completely corresponds to the containment barrier comprises at least one of a stable and controllable containment state and a stable and controllable fuel plant; the corresponding management object with controllable radioactivity comprises at least one of the controllable radioactivity of the containment factory building and the controllable radioactivity of other factory buildings.
2. The method according to claim 1, characterized in that:
If the management element is the primary circuit water device, the corresponding accident mitigation strategy comprises at least one of primary circuit water injection and primary circuit depressurization;
if the management element is heat transfer to the SG, the corresponding accident mitigation strategy includes at least one of water injection to the primary circuit, depressurization of the steam generator, and secondary side heat rejection;
If the management element is heat transfer to the containment, the corresponding accident mitigation strategy includes at least one of flooding the containment, depressurizing the containment, and flooding the reactor pit;
if the management element is a spent fuel pool device, the corresponding accident mitigation strategy comprises water injection to the spent pool;
if the management element is available for spent pool cooling, the corresponding incident mitigation strategy includes restoring spent pool cooling.
3. The method of claim 1, wherein the preset incident diagnostic rules further comprise a risk-free level, the method further comprising:
If one parameter data is in the threshold range corresponding to the risk-free level, accident factors are not acquired for the parameter data.
4. The method of claim 1, wherein said obtaining at least one accident factor based on the measured parameter data and a preset accident diagnosis rule comprises:
obtaining a comparison result of the measured parameter data and a threshold range of the parameter data in the preset accident diagnosis rule;
and obtaining at most one accident factor according to the comparison result for each measured parameter data.
5. The method of claim 4, wherein for each measured parameter data, obtaining at most one accident factor based on the comparison result comprises:
if the measured parameter data is not in the normal range, acquiring 1 accident factor corresponding to the corresponding measured parameter data;
And if the measured parameter data are in the normal range, determining that the corresponding measured parameter data correspond to 0 accident factors.
6. The method according to claim 1, wherein the method further comprises:
executing the accident mitigation strategy;
if the measured parameter data is in the threshold range corresponding to the risk-free level and the preset duration is maintained, the accident management monitoring is stopped.
7. The method according to any one of claims 1-6, wherein determining the accident handling order based on the risk level of the at least one accident factor in the preset accident diagnosis rules and the priority of different parameter data at the same risk level comprises:
acquiring the order of the risk levels;
according to the order of the risk levels from high to low, sequencing the accident factors according to the priority of the parameter data for each risk level;
And integrating the sequenced accident factors to obtain the accident handling sequence.
8. A nuclear power plant incident management apparatus, the apparatus comprising:
The data actual measurement module is used for acquiring actual measurement parameter data of the nuclear power plant in an accident state;
The factor acquisition module is used for acquiring at least one accident factor according to the actually measured parameter data and a preset accident diagnosis rule;
the sequence determining module is used for determining an accident processing sequence according to the risk level of the at least one accident factor in the preset accident diagnosis rule and the priority of different parameter data under the same risk level;
The strategy generation module is used for acquiring an accident mitigation strategy according to the accident handling sequence;
Wherein the apparatus further comprises: the system comprises a parameter data acquisition module, a parameter data processing module and a parameter data processing module, wherein the parameter data acquisition module is used for acquiring parameter data and priority of the parameter data of a nuclear power plant, and the parameter data of the nuclear power plant comprise loop pressure, reactor cavity water level, steam generator water level, loop temperature, site dosage level, containment pressure, containment hydrogen concentration and containment water level; the priority of the parameter data is from high to low: a loop pressure, a reactor cavity water level, a steam generator water level, a loop temperature, a field dose level, a containment pressure, a containment hydrogen concentration, and a containment water level; the risk level acquisition module is used for acquiring at least two risk levels, and each parameter data at least corresponds to two risk levels; the threshold range acquisition module is used for acquiring a threshold range of each risk level corresponding to each parameter data, and each threshold range corresponds to one risk level; the diagnosis rule acquisition module is used for acquiring the preset accident diagnosis rule according to the threshold range, the risk level, the parameter data and the priority of the parameter data;
The policy generation module is specifically configured to: acquiring a plurality of management objects according to the accident management targets of the nuclear power plant; acquiring a plurality of management elements according to the management objects, wherein each management object corresponds to at least one management element; acquiring at least one corresponding accident mitigation operation according to each management element; merging accident mitigation operations corresponding to each management element to obtain a plurality of accident mitigation strategies; acquiring the corresponding relation between the accident mitigation strategy and the accident factors; acquiring a plurality of accident mitigation strategies one by one according to the accident handling sequence and the corresponding relation;
Wherein the management objective includes at least one of decay heat derivation, containment barrier integrity and radioactivity control; the decay heat leading-out corresponding management object comprises at least one of reactor core state controllable stability and spent fuel state controllable stability; the management object which completely corresponds to the containment barrier comprises at least one of a stable and controllable containment state and a stable and controllable fuel plant; the corresponding management object with controllable radioactivity comprises at least one of the controllable radioactivity of the containment factory building and the controllable radioactivity of other factory buildings.
9. 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 7 when the computer program is executed.
10. 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 7.
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Citations (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104915775A (en) * | 2015-06-05 | 2015-09-16 | 国家电网公司 | Risk assessment and emergency decision-making method for forest fire disaster of power transmission line |
| CN105023624A (en) * | 2015-06-09 | 2015-11-04 | 中广核（北京）仿真技术有限公司 | A nuclear power plant serious accident mitigation method and system |
| CN106934510A (en) * | 2015-12-30 | 2017-07-07 | 国核（北京）科学技术研究院有限公司 | Nuclear power plant's accident mitigating system and alleviation method |
| CN111312420A (en) * | 2020-03-02 | 2020-06-19 | 上海交通大学 | Fault diagnosis method and device |
| CN112651633A (en) * | 2020-12-25 | 2021-04-13 | 山东大学 | Tunnel water inrush and mud inrush risk analysis method, system, storage medium and equipment |
| CN112782614A (en) * | 2019-11-11 | 2021-05-11 | 株洲中车时代电气股份有限公司 | Fault early warning method and device of converter based on multi-information fusion |
| CN112950064A (en) * | 2021-03-29 | 2021-06-11 | 国网电力科学研究院有限公司 | Power grid security risk influence factor analysis method and device |
-
2021
- 2021-06-17 CN CN202110674591.0A patent/CN113487464B/en active Active
Patent Citations (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104915775A (en) * | 2015-06-05 | 2015-09-16 | 国家电网公司 | Risk assessment and emergency decision-making method for forest fire disaster of power transmission line |
| CN105023624A (en) * | 2015-06-09 | 2015-11-04 | 中广核（北京）仿真技术有限公司 | A nuclear power plant serious accident mitigation method and system |
| CN106934510A (en) * | 2015-12-30 | 2017-07-07 | 国核（北京）科学技术研究院有限公司 | Nuclear power plant's accident mitigating system and alleviation method |
| CN112782614A (en) * | 2019-11-11 | 2021-05-11 | 株洲中车时代电气股份有限公司 | Fault early warning method and device of converter based on multi-information fusion |
| CN111312420A (en) * | 2020-03-02 | 2020-06-19 | 上海交通大学 | Fault diagnosis method and device |
| CN112651633A (en) * | 2020-12-25 | 2021-04-13 | 山东大学 | Tunnel water inrush and mud inrush risk analysis method, system, storage medium and equipment |
| CN112950064A (en) * | 2021-03-29 | 2021-06-11 | 国网电力科学研究院有限公司 | Power grid security risk influence factor analysis method and device |
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|---|---|
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