CN113487464A - Nuclear power plant accident management method and device, computer equipment and storage medium - Google Patents
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Abstract
The application relates to a nuclear power plant accident management method, a nuclear power plant accident management device, computer equipment and a storage medium. The method comprises the following steps: acquiring actual measurement parameter data of a nuclear power plant in an accident state; then, 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 finally, acquiring an accident mitigation strategy according to the accident handling sequence. By adopting the integrated accident management structure, the diagnosis process is simplified, the problem of frequent jumping and calling in the current accident handling system is avoided, the emergency response speed is improved, the error risk of workers under high pressure is reduced, and the purpose of improving the accident management efficiency of the nuclear power plant can be achieved.
Description
Technical Field
The application relates to the technical field of nuclear power plant accident handling implementation, in particular to a nuclear power plant accident management method, a nuclear power plant accident management device, computer equipment and a storage medium.
Background
If the accident prevention measures of the nuclear power plant fail in the accident development process, accidents will occur, and accident mitigation needs to be implemented. The objective of accident mitigation is to maintain highly damaged core cooling as much 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 plant is reduced as much as possible, and the long-term pollution of soil and underground water is avoided as much as possible. At present, the system structure and the processing scheme of the domestic accident management guide rule are mostly based on the technology of the last 90 years, and an applicable accident management method needs to be researched according to the design characteristics of a third-generation nuclear power plant.
In the current nuclear power plant accident management method, technicians must simultaneously follow two independent and crossed diagnosis systems under an accident, the workload of the technicians is large, and the efficiency of the nuclear power plant accident management is low.
Disclosure of Invention
In view of the above, it is necessary to provide a nuclear power plant accident management method, apparatus, computer device and storage medium capable of improving the efficiency of nuclear power plant accident management.
A nuclear power plant accident management method, the method comprising:
acquiring actual measurement 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 rule is obtained by the following method:
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 primary circuit pressure, a reactor cavity water level, a steam generator water level, a primary circuit temperature, a field 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: primary circuit pressure, reactor cavity water level, steam generator water level, primary circuit temperature, field dosage level, containment vessel pressure, containment vessel hydrogen concentration and containment vessel water level;
acquiring at least two risk levels, wherein each parameter data at least corresponds to two risk levels;
obtaining a threshold range corresponding to each parameter data of each risk level, 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 include a risk-free level, and the method further includes:
if one parameter data is in the threshold range corresponding to the risk-free grade, the accident factor is not acquired from the parameter data.
In one embodiment, the obtaining at least one accident factor according to the measured parameter data and the preset accident diagnosis rule includes:
acquiring a comparison result of the threshold value range of the parameter data in the actual measurement parameter data and the preset accident diagnosis rule;
and acquiring at most one accident factor for each measured parameter data according to the comparison result.
In one embodiment, determining the accident handling sequence according to the accident factor and the preset accident diagnosis rule comprises:
acquiring the high and low orders of the risk levels;
according to the sequence of the risk levels from high to low, aiming at each risk level, sorting accident factors according to the priority of the parameter data;
and integrating the sequenced accident factors to obtain an accident handling sequence.
In one embodiment, obtaining the incident mitigation strategy according to the incident handling order includes:
acquiring a plurality of management objects according to the accident management target 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 factor;
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;
and if the monitored actually-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 quitted.
A nuclear power plant accident 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 measured parameter data and a preset accident diagnosis rule;
the sequence determining module is used for determining an accident handling sequence according to the 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 and a processor, the memory storing a computer program, the processor implementing the following steps when executing the computer program:
acquiring actual measurement 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, on which a computer program is stored which, when executed by a processor, carries out the steps of:
acquiring actual measurement 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 nuclear power plant accident management device, the computer equipment and the storage medium, the actually measured parameter data of the nuclear power plant in the accident state is obtained; then, 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 finally, acquiring an accident mitigation strategy according to the accident handling sequence. Through the integrated accident management structure, the diagnosis process is simplified, the problem that the current accident handling system frequently jumps and calls is solved, the emergency response speed is improved, the error risk of workers under high pressure is reduced, and the purpose of improving the accident management efficiency of the nuclear power plant can be achieved.
Drawings
FIG. 1 is a schematic flow diagram of a nuclear power plant accident management method in one embodiment;
FIG. 2 is a flowchart illustrating a method for obtaining predetermined accident diagnosis rules according to an embodiment;
FIG. 3 is a diagram illustrating a table of predetermined accident diagnosis rules according to an embodiment;
FIG. 4 is a schematic illustration of an accident handling sequence according to another embodiment;
FIG. 5 is a block diagram of a nuclear power plant accident management apparatus according to one embodiment;
FIG. 6 is a diagram illustrating an internal structure of a computer device according to an embodiment.
Detailed Description
In order to make the objects, technical solutions and advantages of the present application more apparent, the present application is described in further detail below with reference to the accompanying drawings and embodiments. It should be understood that the specific embodiments described herein are merely illustrative of the present application and are not intended to limit the present application.
In one embodiment, as shown in fig. 1, a nuclear power plant accident management method is provided, and this embodiment is illustrated by applying the method to a terminal, and it is to be 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 is implemented by interaction between the terminal and the server. In this embodiment, the method includes the steps of:
The nuclear power plant accidents are generally divided into design basis accidents and serious accidents, and the method is mainly used for treating the serious accidents. The serious accident refers to an accident that the reactor core of the nuclear power plant is seriously damaged and the integrity of the containment vessel is possibly damaged, so that the radioactive pollution to the environment and the personal injury and death are caused, and huge loss is generated. The existing nuclear power plant is based on a deep defense principle, is provided with a plurality of barriers and special safety facilities, adopts strict quality management and operator selection training systems, and has strict requirements on site selection of the nuclear power plant, so that the nuclear power plant has strong capacity of resisting external disasters and internal events. Only when multiple failures and operation errors occur in succession, serious accidents can result. Compared with the design benchmark accident of the nuclear power plant which only considers a single fault as a characteristic, a serious accident is an accident that multiple faults are superposed and finally damage to a reactor core occurs. The probability of a serious accident, although low, is not impossible.
Specifically, the actual measurement parameter data of the nuclear power plant in the accident state is obtained through a nuclear power plant monitoring terminal, and the types of the actual measurement parameter data can include a primary circuit pressure, a reactor cavity water level, a steam generator water level, a primary circuit temperature, a field dosage level, a containment pressure, a containment hydrogen concentration, a containment water level and the like.
And 104, acquiring at least one accident factor according to the measured parameter data and a preset accident diagnosis rule.
The accident factor refers to a reason causing the current nuclear power plant accident, and is specifically embodied 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, actual measurement parameter data which is not within a normal threshold range can be obtained by comparing the actual measurement parameter data with the plurality of threshold ranges, an accident factor can be determined according to the actual measurement parameter data, and one actual measurement parameter data corresponds to one accident factor under a common condition.
And step 106, determining an accident handling sequence according to the accident factor and a preset accident diagnosis rule.
The accident handling sequence refers to a handling sequence of accident factors.
Specifically, dimensions such as the influence range of the release of the accident factors from fission products, the threat degree of the integrity of the containment vessel, the decay heat derivation scheme, the long-term stability and controllability of the state of the power plant and the like can be evaluated in the preset accident diagnosis rule, so that the risk level of the accident factors can be obtained, and the accident caused by the accident factors with higher risk can be preferentially processed. And if a plurality of accident factors exist, processing each accident factor from high to low according to the risk level. The preset accident diagnosis rules also can be used for carrying out priority distribution on the parameter data of the nuclear power plant, and because the reasons, positions and solutions of accidents corresponding to each parameter data are different, accident factors related to the parameter data with high priority can be processed preferentially under the same risk level.
And 108, acquiring an accident mitigation strategy according to the accident handling sequence.
The accident mitigation strategy refers to an operation and an action which are required to be performed for solving an overrun accident factor, and the operation and the action are called accident mitigation operation. A plurality of incident mitigation operations are typically included in an incident mitigation strategy.
Specifically, typically, one incident mitigation strategy corresponds to one incident factor. And when a plurality of accident factors exceed the limit, acquiring accident mitigation strategies one by one according to the accident handling sequence.
In the nuclear power plant accident management method, actual measurement parameter data of the nuclear power plant in an accident state is obtained; then, 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 finally, acquiring an accident mitigation strategy according to the accident handling sequence. Through the integrated accident management structure, the diagnosis process is simplified, the problem that the current accident handling system frequently jumps and calls is solved, the emergency response speed is improved, the error risk of workers under high pressure is reduced, and the purpose of improving the accident management efficiency of the nuclear power plant can be achieved.
In one embodiment, as shown in fig. 2, the preset accident diagnosis rule is obtained by the following method:
202, acquiring parameter data of a nuclear power plant and priority of the parameter data, wherein the parameter data of the nuclear power plant comprises primary circuit pressure, reactor cavity water level, steam generator water level, primary circuit temperature, field dosage level, containment pressure, containment hydrogen concentration and containment water level; the priority of the parameter data is from high to low: primary circuit pressure, reactor cavity water level, steam generator water level, primary circuit temperature, field dose level, containment vessel pressure, containment vessel hydrogen concentration, and containment vessel water level.
Specifically, parameter data of the nuclear power plant are obtained, priority ranking is conducted on the parameter data, the parameter data with the highest priority ranking is the parameter data with the highest priority ranking, and the parameter data with the highest priority ranking means that the accident factor related to the parameter data is the highest in the releasing priority ranking. The priority of the parameter data is respectively from top to bottom: primary circuit pressure, reactor cavity water level, steam generator water level, primary circuit temperature, field dose level, containment vessel pressure, containment vessel hydrogen concentration, and containment vessel water level.
And 204, acquiring at least two risk levels, wherein each parameter data at least corresponds to 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 situation of the nuclear power plant.
Specifically, a threshold range is set for each risk level corresponding to each parameter data. And if the measured value of a certain measured parameter data is within a threshold range of a risk level, determining that the measured parameter data is in the risk level.
And 208, acquiring 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 practical use, the preset accident diagnosis rule can be embodied in a table mode. For example, as shown in the preset accident diagnosis rule table shown in fig. 3, the first column is set as parameter data (primary circuit pressure, reactor cavity water level, steam generator water level, primary circuit temperature, field dose level, containment pressure, containment hydrogen concentration, and containment water level) arranged from top to bottom according to priority, the first row is set as risk levels (risk level 1, risk level 2, risk level 3, and risk level 4) arranged from top to bottom according to risk, one cell filled with a threshold range reflects the threshold range of the risk level list corresponding to the parameter data of the row, and an empty cell indicates that the parameter data of the row is not provided with the risk level list. The risk level can be selected from red, orange, yellow and green to be marked from high to low, so that the high risk level is more visual and striking.
In the embodiment, the parameter data of the nuclear power plant and the priority of the parameter data are obtained; then, at least two risk levels are obtained, and each parameter data at least corresponds to the 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 rule to treat the nuclear power plant accident, the diagnosis process is simplified, the problems of frequent jumping and calling in the current accident treatment system are solved, the emergency response speed is improved, the error risk of workers under high pressure is reduced, and the purpose of improving the accident management efficiency of the nuclear power plant can be achieved.
In one embodiment, the preset accident diagnosis rules further include a risk-free level, and the method further includes: if one parameter data is in the threshold range corresponding to the risk-free grade, the accident factor is not acquired from the parameter data.
Specifically, a threshold range corresponding to the risk-free level of one parameter data is a normal range of the parameter data. As shown in the table of the preset accident diagnosis rule shown in fig. 3, the risk level 4 in the fourth column is a risk-free level, and if the parameter data is within the threshold range of the risk level 4, the accident factor is not obtained from the parameter data.
In one embodiment, the obtaining of the at least one accident factor based on the measured parameter data and the preset accident diagnosis rules comprises: acquiring a comparison result of the threshold value range of the parameter data in the actual measurement parameter data and the preset accident diagnosis rule; and acquiring at most one accident factor for each measured parameter data according to the comparison result.
Specifically, after the actual measurement parameter data is obtained, each actual measurement parameter data is 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 for 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, the accident factor is not acquired from the measured parameter data. Therefore, when one parameter data is in the normal range, the parameter data corresponds to 0 accident factor, and when one parameter data is not in the normal range, the parameter data corresponds to 1 accident factor.
In one embodiment, determining the accident handling order according to the accident factor and the preset accident diagnosis rule comprises: acquiring the high and low orders of the risk levels; according to the sequence of the risk levels from high to low, aiming at each risk level, sorting accident factors according to the priority of the parameter data; 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 level of the parameter data, wherein the accident factors corresponding to the parameter data with high priority level are arranged in the front. And then, similarly, all accident factors in the second high risk level are acquired and sorted according to the priority level of the parameter data. And sequencing the accident factors in the lowest risk level according to the priority level of the parameter data until all the accident factors of the lowest risk level are obtained. 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 used, the accident handling sequence is shown in fig. 4, and is performed in the order from top to bottom, starting from the first column, column by column.
In the embodiment, the high and low orders of the risk levels are obtained; then according to the sequence of the risk levels from high to low, aiming at each risk level, sorting accident factors according to the priority of the parameter data; and finally integrating the sorted accident factors to obtain an accident handling sequence. By using the accident handling sequence to handle the nuclear power plant accidents, high-risk accidents are preferentially handled, the problems of frequent jumping and calling in the conventional accident handling system are avoided, the error risk of workers under high pressure is reduced, and the purpose of improving the accident management efficiency of the nuclear power plant can be achieved.
In one embodiment, obtaining the incident mitigation strategy according to the incident handling order comprises: acquiring a plurality of management objects according to the accident management target 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 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.
In particular, nuclear power plant accident management objectives refer to certain conditions that a nuclear power plant needs to achieve. For example, decay heat removal, 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 and the spent fuel state are controllable and stable. Then at least one management element of each management object is determined respectively, corresponding accident mitigation operations are formulated according to the management elements, and each management element can correspond to a plurality of accident mitigation operations to deal 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 acquiring the corresponding relation between the accident mitigation strategy and the accident factor according to the accident mitigation strategy which can specifically solve the accident factor, wherein under the normal condition, the accident factors with different risk levels corresponding to one parameter data can adopt one accident mitigation strategy. And finally, acquiring the accident mitigation strategies one by one according to the accident handling sequence, and preparing to execute the accident mitigation strategies in sequence.
As an example, when the preset accident diagnosis rule table shown in fig. 3 is used, an accident mitigation strategy may be configured for each parameter data, where each accident mitigation strategy is respectively represented as SAS1, SAS2, SAS3, SAS4, SAS5, SAS6, SAS7, and SAS8, and corresponds to a primary circuit pressure, a reactor cavity level, a steam generator level, a primary circuit temperature, a field dose level, a containment pressure, a containment hydrogen concentration, and a containment level. Sequentially acquiring 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) → SAS-8 (risk level 3) according to the accident handling sequence, since the risk level 4 is a risk-free level, there is no accident factor, so there is no need to obtain an accident mitigation strategy. In the actual implementation process, each parameter data of the nuclear power plant is a determined value (such as containment pressure), so each measured parameter data can only fall into one risk level, and therefore, in one accident management process, one accident mitigation strategy can only be used once, and the problem of repeated use of the same accident mitigation strategy in two sets of accident management logics at present is solved.
In one embodiment, the nuclear power plant accident management method further includes: executing an accident mitigation strategy; and if the monitored actually-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 quitted.
The accident management monitoring refers to a process from obtaining measured parameter data of the nuclear power plant in an accident state to obtaining at least one accident factor according to the measured parameter data and a preset accident diagnosis rule.
Specifically, a plurality of accident mitigation strategies are executed according to an accident handling sequence, or an accident management guide rule is generated according to the accident handling sequence and the plurality of accident mitigation strategies, and then the accident management guide rule is executed. And if all the measured parameter data are monitored to be in the threshold range corresponding to the risk-free level and the preset duration is maintained, the accident management monitoring is quitted. For example, the states of the reactor core \ spent fuel pool and the containment vessel are stable and controllable for a long time (such as 24h or 72h), and can be expected to be kept continuously, at the moment, all parameter data are within a normal range, all parameter data are in a risk-free grade, the number of the acquired accident factors is 0, and the accident management monitoring is quitted.
It should be understood that although the various steps in the flow charts of fig. 1-2 are shown in order as indicated by the arrows, the steps are not necessarily performed in order as indicated by the arrows. The steps are not performed in the exact order shown and described, and may be performed in other orders, unless explicitly stated otherwise. Moreover, at least some of the steps in fig. 1-2 may include multiple steps or multiple stages, which are not necessarily performed at the same time, but may be performed at different times, which are not necessarily performed in sequence, but may be performed in turn or alternately with other steps or at least some of the other steps.
In one embodiment, as shown in fig. 5, there is provided a nuclear power plant accident management apparatus 500, including: a data actual measurement module 501, a factor acquisition module 502, a sequence determination module 503 and a policy generation module 504, wherein:
and the data actual measurement module 501 is used for acquiring 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 also comprises a risk-free grade, and if one parameter data is in a threshold range corresponding to the risk-free grade, the accident factor is not acquired from the parameter data.
And the sequence determining module 503 is configured to determine an accident handling sequence according to the accident factor and a preset accident diagnosis rule.
And a policy generation module 504, configured to obtain an accident mitigation policy according to the accident handling sequence.
In one embodiment, the apparatus further comprises:
the nuclear power plant parameter data acquisition module is used for acquiring parameter data of a nuclear power plant and priority of the parameter data, wherein the parameter data of the nuclear power plant comprise primary circuit pressure, reactor cavity water level, steam generator water level, primary circuit temperature, field dosage level, containment pressure, containment hydrogen concentration and containment water level; the priority of the parameter data is from high to low: primary circuit pressure, reactor cavity water level, steam generator water level, primary circuit temperature, field dose level, containment vessel pressure, containment vessel hydrogen concentration, and containment vessel water level.
And the risk grade acquisition module is used for acquiring at least two risk grades, and each parameter data at least corresponds to the two risk grades.
And the threshold range acquisition module is used for acquiring a threshold range corresponding to each parameter data of each risk level, and each threshold range corresponds to one risk level.
And the diagnosis rule obtaining module is used for obtaining 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 the parameter data in the preset accident diagnosis rule; and acquiring at most one accident factor for each measured parameter data according to the comparison result.
In one embodiment, the order determination module 503 is further configured to obtain a high-low order of risk levels; according to the sequence of the risk levels from high to low, aiming at each risk level, sorting accident factors according to the priority of the parameter data; 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 accident 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 factor; 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; and if the monitored actually-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 quitted.
For specific definition of the nuclear power plant accident management device, reference may be made to the above definition of the nuclear power plant accident management method, which is not described herein again. All or part of each module in the nuclear power plant accident management device can be realized by software, hardware and a combination thereof. The modules can be embedded in a hardware form or independent from a processor in the computer device, and can also be stored in a memory in the computer device in a software form, so that the processor can call and execute operations corresponding to the modules.
In one embodiment, a computer device is provided, which may be a terminal, and its internal structure diagram 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 comprises a nonvolatile 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 an operating system and computer programs in the non-volatile storage medium. The communication interface of the computer device is used for carrying out wired or wireless communication with an external terminal, and the wireless communication can be realized through WIFI, an operator network, NFC (near field communication) or other technologies. The computer program is executed by a processor to implement a nuclear power plant accident management method. 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, a key, a track ball or a touch pad arranged on the shell of the computer equipment, an external keyboard, a touch pad or a mouse and the like.
Those skilled in the art will appreciate that the architecture shown in fig. 6 is merely a block diagram of some of the structures associated with the disclosed aspects and is not intended to limit the computing devices to which the disclosed aspects apply, as particular computing devices may include more or less components than those shown, or may combine certain 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 a computer program stored therein, the processor implementing the following steps when executing the computer program:
acquiring actual measurement 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 a nuclear power plant, wherein the parameter data of the nuclear power plant comprises a primary circuit pressure, a reactor cavity water level, a steam generator water level, a primary circuit temperature, a field 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: primary circuit pressure, reactor cavity water level, steam generator water level, primary circuit temperature, field dosage level, containment vessel pressure, containment vessel hydrogen concentration and containment vessel water level;
acquiring at least two risk levels, wherein each parameter data at least corresponds to two risk levels;
obtaining a threshold range corresponding to each parameter data of each risk level, 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 also comprises a risk-free grade, and if one parameter data is in a threshold range corresponding to the risk-free grade, the accident factor is not acquired from the parameter data.
In one embodiment, the processor, when executing the computer program, further performs the steps of:
acquiring a comparison result of the threshold value range of the parameter data in the actual measurement parameter data and the preset accident diagnosis rule;
and acquiring at most one accident factor for each measured parameter data according to the comparison result.
In one embodiment, the processor, when executing the computer program, further performs the steps of:
acquiring the high and low orders of the risk levels;
according to the sequence of the risk levels from high to low, aiming at each risk level, sorting accident factors according to the priority of the parameter data;
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 target 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 factor;
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;
and if the monitored actually-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 quitted.
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:
acquiring actual measurement 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 a nuclear power plant, wherein the parameter data of the nuclear power plant comprises a primary circuit pressure, a reactor cavity water level, a steam generator water level, a primary circuit temperature, a field 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: primary circuit pressure, reactor cavity water level, steam generator water level, primary circuit temperature, field dosage level, containment vessel pressure, containment vessel hydrogen concentration and containment vessel water level;
acquiring at least two risk levels, wherein each parameter data at least corresponds to two risk levels;
obtaining a threshold range corresponding to each parameter data of each risk level, 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 also comprises a risk-free grade, and if one parameter data is in a threshold range corresponding to the risk-free grade, the accident factor is not acquired from the parameter data.
In one embodiment, the computer program when executed by the processor further performs the steps of:
acquiring a comparison result of the threshold value range of the parameter data in the actual measurement parameter data and the preset accident diagnosis rule;
and acquiring at most one accident factor for each measured parameter data according to the comparison result.
In one embodiment, the computer program when executed by the processor further performs the steps of:
acquiring the high and low orders of the risk levels;
according to the sequence of the risk levels from high to low, aiming at each risk level, sorting accident factors according to the priority of the parameter data;
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 target 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 factor;
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;
and if the monitored actually-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 quitted.
It will be understood by those skilled in the art that all or part of the processes of the methods of the embodiments described above can be implemented by hardware instructions of a computer program, which can be stored in a non-volatile computer-readable storage medium, and when executed, can include the processes of the embodiments of the methods described above. Any reference to memory, storage, database or other medium used in the embodiments provided herein can include at least one of non-volatile and volatile memory. Non-volatile Memory may include Read-Only Memory (ROM), magnetic tape, floppy disk, flash Memory, optical storage, or the like. Volatile Memory can include Random Access Memory (RAM) or external cache Memory. By way of illustration and not limitation, RAM can take many forms, such as Static Random Access Memory (SRAM) or Dynamic Random Access Memory (DRAM), among others.
The technical features of the above embodiments can be arbitrarily combined, and for the sake of brevity, all possible combinations of the technical features in the above embodiments are not described, but should be considered as the scope of the present specification as long as there is no contradiction between the combinations of the technical features.
The above-mentioned embodiments only express several embodiments of the present application, and the description thereof is more specific and detailed, but not construed as limiting the scope of the invention. It should be noted that, for a person skilled in the art, several variations and modifications can be made without departing from the concept of the present application, which falls within the scope of protection of the present application. Therefore, the protection scope of the present patent shall be subject to the appended claims.
Claims (10)
1. A nuclear power plant accident management method, characterized in that the method comprises:
acquiring actual measurement 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 the accident factor and the preset accident diagnosis rule;
and acquiring an accident mitigation strategy according to the accident handling sequence.
2. The method according to claim 1, wherein the preset accident diagnosis rule is obtained by:
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 primary circuit pressure, a reactor cavity water level, a steam generator water level, a primary circuit temperature, a field dose level, a containment pressure, a containment hydrogen concentration and a containment water level; the priority of the parameter data is from high to low as: primary circuit pressure, reactor cavity water level, steam generator water level, primary circuit temperature, field dosage level, containment vessel pressure, containment vessel hydrogen concentration and containment vessel water level;
acquiring at least two risk levels, wherein each parameter data at least corresponds to two risk levels;
obtaining a threshold range corresponding to each parameter data of each risk level, wherein each threshold range corresponds to one risk level;
and acquiring the preset accident diagnosis rule according to the threshold range, the risk level, the parameter data and the priority of the parameter data.
3. The method of claim 2, wherein the preset incident diagnostic rules further include a no risk level, the method further comprising:
if one parameter data is in the threshold range corresponding to the risk-free grade, the accident factor is not acquired from the parameter data.
4. The method according to claim 2, wherein the obtaining at least one accident factor based on the measured parameter data and preset accident diagnosis rules comprises:
acquiring a comparison result of the threshold ranges of the measured parameter data and the parameter data in the preset accident diagnosis rule;
and acquiring at most one accident factor for each measured parameter data according to the comparison result.
5. The method according to claim 2, wherein the determining an accident handling order according to the accident factor and the preset accident diagnosis rule comprises:
acquiring the high and low orders of the risk levels;
according to the sequence of the risk levels from high to low, aiming at each risk level, sequencing the accident factors according to the priority of the parameter data;
and integrating the sequenced accident factors to obtain the accident handling sequence.
6. The method of claim 1, wherein obtaining incident mitigation strategies according to the incident processing order comprises:
acquiring a plurality of management objects according to the accident management target 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 factor;
and acquiring a plurality of accident mitigation strategies one by one according to the accident handling sequence and the corresponding relation.
7. The method of claim 1, further comprising:
executing the incident mitigation strategy;
and if the monitored actually-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 quitted.
8. A nuclear power plant accident management apparatus, characterised in that the apparatus comprises:
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 measured parameter data and a preset accident diagnosis rule;
the sequence determining module is used for determining an accident handling sequence according to the accident factor and the preset accident diagnosis rule;
and the strategy generation module is used for acquiring the accident mitigation strategy according to the accident handling sequence.
9. A computer device comprising a memory and a processor, the memory storing a computer program, characterized in that the processor, when executing the computer program, implements the steps of the method of any of claims 1 to 7.
10. A computer-readable storage medium, on which a computer program is stored, which, when being executed by a processor, carries out the steps of the method of any one of claims 1 to 7.
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