CN112530616A - Method and device for judging emergency operation regulations of nuclear power station - Google Patents

Method and device for judging emergency operation regulations of nuclear power station Download PDF

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CN112530616A
CN112530616A CN201910883928.1A CN201910883928A CN112530616A CN 112530616 A CN112530616 A CN 112530616A CN 201910883928 A CN201910883928 A CN 201910883928A CN 112530616 A CN112530616 A CN 112530616A
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information
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CN112530616B (en
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李宁
马建新
彭立
胡俊
董晓峰
王桂兰
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China Techenergy Co Ltd
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    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21DNUCLEAR POWER PLANT
    • G21D3/00Control of nuclear power plant
    • G21D3/04Safety arrangements
    • G21D3/06Safety arrangements responsive to faults within the plant
    • YGENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
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Abstract

The invention discloses a method and a device for judging emergency operation regulations of a nuclear power station, wherein the method comprises the following steps: collecting the on-site state information of the nuclear power station, and accepting the checking information input by a user; determining an execution path of procedure selection nodes in a digital model corresponding to the procedure flow chart according to the state information and the check information; starting a starting node of the digital model, executing a procedure selection node, and acquiring information of a procedure page to be executed. The method improves the working efficiency.

Description

Method and device for judging emergency operation regulations of nuclear power station
Technical Field
The invention relates to the technical field of nuclear power stations, in particular to a method and a device for judging emergency operation regulations of a nuclear power station.
Background
At present, emergency operation regulations of nuclear power plants are an important factor for ensuring safe operation of nuclear power plants. When an accident occurs in the nuclear power plant, an operator needs to check information transmitted by a monitor system display and combine a flow chart file corresponding to an emergency operation rule to judge and select rule pages to be executed under different accident conditions, and then corresponding recovery operation is performed according to the emergency operation rule aiming at the accident.
The emergency operation regulations for building the nuclear power station in early domestic and corresponding flow chart files usually depend on paper version files in use, the electronization degree is low, under the accident condition, the equipment does not have the functions of automatically calculating and judging the regulation page to be executed, the corresponding regulation page can be finally determined after the calculation and judgment are manually performed by a power station operator, and the defects of large workload, time and labor waste and the like are overcome. That is, under the accident condition, the monitoring system device does not have the functions of automatically calculating according to the procedure flow chart and judging the procedure page to be executed, but depends on manual calculation and judgment, and the working efficiency is too low.
Disclosure of Invention
The invention aims to provide a method and a device for judging emergency operation regulations of a nuclear power station, so as to improve the working efficiency.
In order to solve the technical problem, the invention provides a method for judging emergency operation regulations of a nuclear power station, which comprises the following steps:
collecting the on-site state information of the nuclear power station, and accepting the checking information input by a user;
determining an execution path of procedure selection nodes in a digital model corresponding to the procedure flow chart according to the state information and the check information; the procedure selection node comprises a state node and a check node; the digital model is a cyclic tree structure and comprises a starting node, a plurality of procedure selecting nodes and a plurality of procedure page nodes;
starting a starting node of the digital model, executing a procedure selection node, and acquiring information of a procedure page to be executed.
Preferably, the method further comprises:
and updating the state information and the check information input by the user at intervals of preset time, restarting a starting node of the digital model, executing a procedure selection node, and acquiring new procedure page information to be executed.
Preferably, the determining, according to the state information and the check information, an execution path of the procedure selection node corresponding to the procedure flowchart includes:
judging whether the state information meets the node condition of the state node, if so, determining the value of the state node to be 1, and executing a path corresponding to the value 1; if not, determining that the numerical value of the state node is 0, and executing a path corresponding to the numerical value 0;
judging whether the checking information meets the node condition of the checking node, if so, determining the value of the checking node to be 1, and executing a path corresponding to the value 1; if not, determining that the value of the check node is 0, and executing a path corresponding to the value 0.
Preferably, after the acquiring the protocol page information to be executed, the method further includes:
and displaying the procedure page information to be executed and the fault state corresponding to the procedure page information.
The invention also provides a device for judging the emergency operation regulations of the nuclear power station, which is used for realizing the method and comprises the following steps:
the acquisition module is used for acquiring the on-site state information of the nuclear power station and receiving the checking information input by a user;
a path determining module, configured to determine, according to the state information and the check information, an execution path of a procedure selection node in a digital model corresponding to the procedure flowchart; the procedure selection node comprises a state node and a check node; the digital model is a cyclic tree structure and comprises a starting node, a plurality of procedure selecting nodes and a plurality of procedure page nodes;
and the starting module is used for starting the starting node of the digital model, executing the procedure selection node and acquiring the information of the procedure page to be executed.
Preferably, the apparatus further comprises:
and the updating module is used for updating the state information and the check information input by the user at intervals of preset time, restarting a starting node of the digital model, executing a procedure selection node and acquiring new procedure page information to be executed.
Preferably, the determining the path module includes:
the first judging unit is used for judging whether the state information meets the node condition of the state node, if so, the value of the state node is determined to be 1, and a path corresponding to the value 1 is executed; if not, determining that the numerical value of the state node is 0, and executing a path corresponding to the numerical value 0;
the second judging unit is used for judging whether the checking information meets the node condition of the checking node, if so, the value of the checking node is determined to be 1, and the path corresponding to the value 1 is executed; if not, determining that the value of the check node is 0, and executing a path corresponding to the value 0.
Preferably, the apparatus further comprises:
and the display module is used for displaying the procedure page information to be executed and the fault state corresponding to the procedure page information.
The method and the device for judging the emergency operation procedures of the nuclear power station, provided by the invention, are used for collecting the on-site state information of the nuclear power station and receiving the checking information input by a user; determining an execution path of procedure selection nodes in a digital model corresponding to the procedure flow chart according to the state information and the check information; the procedure selection node comprises a state node and a check node; the digital model is a cyclic tree structure and comprises a starting node, a plurality of procedure selecting nodes and a plurality of procedure page nodes; starting a starting node of the digital model, executing a procedure selection node, and acquiring information of a procedure page to be executed. Therefore, the emergency operation rule is executed according to the digital model, the rule page to be executed is automatically selected according to the actual field acquisition data and the manual checking state of the operator, the rule page to be executed is automatically selected in the actual use of the nuclear power unit, manual complicated calculation and judgment are not needed, and the working efficiency is improved.
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In order to more clearly illustrate the embodiments of the present invention or the technical solutions in the prior art, the drawings used in the description of the embodiments or the prior art will be briefly described below, it is obvious that the drawings in the following description are only embodiments of the present invention, and for those skilled in the art, other drawings can be obtained according to the provided drawings without creative efforts.
FIG. 1 is a flow chart of a method for determining emergency operation procedures of a nuclear power plant according to the present invention;
FIG. 2 is a diagram of nodes and corresponding digital models in a procedure flow diagram;
FIG. 3 is a schematic view of a procedure page information display;
fig. 4 is a flowchart of a device for determining an emergency operation procedure of a nuclear power plant according to the present invention.
Detailed Description
The core of the invention is to provide a method and a device for judging emergency operation regulations of a nuclear power station, so as to improve the working efficiency.
In order to make the technical solutions of the present invention better understood, the technical solutions in the embodiments of the present invention will be clearly and completely described below with reference to the drawings in the embodiments of the present invention, and it is obvious that the described embodiments are only a part of the embodiments of the present invention, and not all of the embodiments. All other embodiments, which can be derived by a person skilled in the art from the embodiments given herein without making any creative effort, shall fall within the protection scope of the present invention.
Referring to fig. 1, fig. 1 is a flowchart of a method for determining an emergency operation procedure of a nuclear power plant according to the present invention, where the method includes the following steps:
s11: collecting the on-site state information of the nuclear power station, and accepting the checking information input by a user;
s12: determining an execution path of procedure selection nodes in a digital model corresponding to the procedure flow chart according to the state information and the check information;
the procedure selection node comprises a state node and a check node; the digital model is a cyclic tree structure and comprises a starting node, a plurality of procedure selecting nodes and a plurality of procedure page nodes;
s13: starting a starting node of the digital model, executing a procedure selection node, and acquiring information of a procedure page to be executed.
Therefore, the method executes the emergency operation rule according to the digital model, automatically selects the rule page to be executed according to the actual field acquisition data and the manual checking state of the operator, automatically selects the rule page to be executed in the actual use of the nuclear power unit, does not need manual complicated calculation and judgment, and improves the working efficiency.
Based on the method, the method further comprises the following steps;
s14: and updating the state information and the checking information input by the user at intervals of preset time, restarting a starting node of the digital model, executing a procedure selection node, and acquiring new procedure page information to be executed.
Wherein the preset time is 500 milliseconds or 1 second.
Therefore, the method can automatically select the procedure page to be executed, and can also automatically select a new procedure page when the field working condition, namely the state information and the checking information, changes. The method is continuous and periodic in calculation, and automatically judges and selects the procedure page to be executed.
Further, the process of step S12 specifically includes the following steps:
s1: judging whether the state information meets the node condition of the state node, if so, determining the value of the state node to be 1, and executing a path corresponding to the value 1; if not, determining that the numerical value of the state node is 0, and executing a path corresponding to the numerical value 0;
s2: judging whether the checking information meets the node condition of the checking node, if so, determining the value of the checking node to be 1, and executing a path corresponding to the value 1; if not, determining that the value of the check node is 0, and executing a path corresponding to the value 0.
Further, in step S13, after the information of the procedure page to be executed is acquired, the method further includes: and displaying the procedure page information to be executed and the fault state corresponding to the procedure page information.
Further, step S11 is preceded by: and establishing a digital module according to the procedure flow chart.
In detail, the digital model is established according to a rule flow chart, the digital model is found to correspond to a tree-shaped data structure through an emergency operation rule and a corresponding flow chart file, the tree-shaped data structure is provided with a starting node, a left path and a right path are arranged with each judgment node, the tree-shaped data structure is connected to the next judgment node according to field conditions, and finally, the tree-shaped data structure is ended with a rule page node, namely, a rule page under a corresponding working condition is selected. When the variable value of a certain node in the last path is changed, the path is changed until a new procedure page is reached.
Under the normal working condition of the nuclear power unit, according to the flow chart logic requirements corresponding to the emergency accident regulations, the method does not select the regulation page, but directly returns to the starting node to perform the next cycle of cycle calculation.
Referring to fig. 2, fig. 2 shows nodes and corresponding digital models in the procedure flow chart, a part of the procedure flow is shown on the left side of fig. 2, and the digital models corresponding to the procedure flow on the left side are shown on the right side of fig. 2, so that the nodes and corresponding data models in the node flow chart can be seen. The description in the digital model is omitted for ellipses in the figure, and the description in the digital model is whether the state information meets the node condition of the state node or not, or whether the checking information meets the node condition of the checking node or not. For example, a value of 1 in the starting node1 corresponds to the description: the judgment of 'at least one DOS alarm appears or LBJ002A appears in a T20 disc' is true; a value of 0 in the start node1 corresponds to the description: the "at least one DOS alarm present or LBJ002A present in the T20 disc" is judged false. Describing whether the node state meets the node condition, if so, the value is 1, executing the next node corresponding to 1, if not, the value is 0, and executing the next node corresponding to 0. LBJ002A represents a field fault, where like alphanumeric numbers represent faults and different numbers represent different faults.
The starting node is an entry of the whole flowchart, each loop execution is started from the entry, only one starting node is provided, and the executable path is divided into a left path and a right path according to the node value as a judgment condition.
The procedure selection node has 1 inlet and 2 outlets, and when the node condition is met, namely the value is 1, an execution path is provided; when the node condition is not satisfied, i.e., the value is 0, there is another execution path.
The rule node judgment conditions are divided into two types: one is automatically calculated from the results of logic equation calculations of variables, such procedures selecting node representations, for example
Figure BDA0002205553550000061
Or
Figure BDA0002205553550000062
The other is that the state is modified by manual intervention of an operator in a checking mode, the checked variable value is 'TRUE', and the variable value which is not checked is 'FALSE'; such procedure selection node representation, for example
Figure BDA0002205553550000063
Wherein, the procedure page node corresponds to the selected procedure page information, for example: PS02 page one, such nodes do not need to make any further decisions.
The computer models established by the three types of nodes are shown in fig. 3, when the three types of nodes are finally realized, the conditions of the left and right nodes are judged by the process and are configured in the form of database variable points, and when the emergency operation procedure flow chart file is updated, the configuration file is modified, so that the maintenance is convenient, the calculation is continuously and periodically carried out, and the procedure page to be executed is automatically judged and selected.
The flow chart of the accident regulation is mainly characterized in that the flow chart is of a circular tree structure, condition variables are automatically calculated in the field state, manual operation of operators, namely hooking and hooking cancellation, is used as input information for collection, and regulation selection calculation is continuously and periodically realized: and according to the node flow chart, judging the numerical values of the nodes to be 0 and 1 by each rule, selecting the next node, and finally selecting a 'rule page node', or directly entering the next cycle calculation without selecting any rule page node under normal working conditions. The calculation period can be set to 500 milliseconds or 1 second, so that the calculation can be completed quickly when the working condition of the unit changes, and corresponding new rule page information is selected.
In detail, in step S13, after the procedure page information to be executed is acquired, the procedure page information to be executed and the fault state corresponding to the procedure page information are displayed. Wherein, after automatically determining the procedure page information to be executed, the computer technology can be used to display the determination result in combination with the operator requirement, referring to fig. 3, for example, "PS 01" corresponds to the flowchart
Figure BDA0002205553550000071
The display mode that can be adopted is that after a certain rule page is selected, when the corresponding variable is "1", the boxes in front of the rule page are filled to indicate the current working condition and the serial number of the executable rule page, the currently displayed rule page information in fig. 3 is PS01, and the fault state corresponding to PS01 is 6.6KV loss.
The method is based on a computer model, takes later maintenance into consideration, is convenient to modify, and carries out periodic and cyclic automatic judgment according to actual field data acquisition and manual state selection of an operator. The method can automatically select the rule pages to be executed in the practical use of the nuclear power unit, reduce the calculation amount of operators, and assist the operators to quickly and accurately find the rule pages to be executed under the operation condition. According to the method, the emergency operation regulation of the nuclear power plant and the corresponding flow chart are modeled and automatically judged, so that the workload of manual calculation of an operator can be greatly reduced, the speed and accuracy of regulation selection judgment are improved, the workload of the operator of the nuclear power plant is reduced, the working efficiency is improved, and the safe operation of the nuclear power plant can be further ensured.
Referring to fig. 4, fig. 4 is a flowchart of a device for determining emergency operation procedures of a nuclear power plant according to the present invention, the device is configured to implement the method described above, and the device includes:
the acquisition module 101 is used for acquiring the on-site state information of the nuclear power station and receiving the check information input by a user;
a path determining module 102, configured to determine, according to the state information and the check information, an execution path of a procedure selection node in the digital model corresponding to the procedure flowchart; the procedure selection node comprises a state node and a check node; the digital model is a cyclic tree structure and comprises a starting node, a plurality of procedure selecting nodes and a plurality of procedure page nodes;
the starting module 103 is configured to start a starting node of the digital model, execute a procedure selection node, and acquire procedure page information to be executed.
Therefore, the device executes the emergency operation rules according to the digital model, automatically selects the rule pages to be executed according to the actual field acquisition data and the manual checking state of the operator, automatically selects the rule pages to be executed in the actual use of the nuclear power unit, does not need manual complicated calculation and judgment, and improves the working efficiency.
Based on the above device, further, still include: and the updating module is used for updating the state information and the check information input by the user at intervals of preset time, restarting a starting node of the digital model, executing a procedure selection node and acquiring new procedure page information to be executed. Therefore, when the field working condition, namely the state information and the checking information, changes, the device can automatically select a new rule page.
Further, the determine path module includes:
the first judging unit is used for judging whether the state information meets the node condition of the state node, if so, the numerical value of the state node is determined to be 1, and a path corresponding to the numerical value 1 is executed; if not, determining that the numerical value of the state node is 0, and executing a path corresponding to the numerical value 0;
the second judgment unit is used for judging whether the checking information meets the node condition of the checking node, if so, the value of the checking node is determined to be 1, and the path corresponding to the value 1 is executed; if not, determining that the value of the check node is 0, and executing a path corresponding to the value 0.
Further, the apparatus further comprises: and the display module is used for displaying the procedure page information to be executed and the fault state corresponding to the procedure page information.
Therefore, the device can automatically select the procedure page to be executed, and when the field working condition, namely the state information and the checking information, changes, the method can also automatically select a new procedure page. Namely, the device continuously and periodically calculates, and automatically judges and selects the rule page to be executed.
The embodiments are described in a progressive manner, each embodiment focuses on differences from other embodiments, and the same or similar parts among the embodiments are referred to each other. The device disclosed by the embodiment corresponds to the method disclosed by the embodiment, so that the description is simple, and the relevant points can be referred to the method part for description.
Those of skill would further appreciate that the various illustrative elements and algorithm steps described in connection with the embodiments disclosed herein may be implemented as electronic hardware, computer software, or combinations of both, and that the various illustrative components and steps have been described above generally in terms of their functionality in order to clearly illustrate this interchangeability of hardware and software. Whether such functionality is implemented as hardware or software depends upon the particular application and design constraints imposed on the implementation. Skilled artisans may implement the described functionality in varying ways for each particular application, but such implementation decisions should not be interpreted as causing a departure from the scope of the present invention.
The steps of a method or algorithm described in connection with the embodiments disclosed herein may be embodied directly in hardware, in a software module executed by a processor, or in a combination of the two. A software module may reside in Random Access Memory (RAM), memory, Read Only Memory (ROM), electrically programmable ROM, electrically erasable programmable ROM, registers, hard disk, a removable disk, a CD-ROM, or any other form of storage medium known in the art.
The method and the device for judging the emergency operation regulations of the nuclear power station provided by the invention are described in detail above. The principles and embodiments of the present invention are explained herein using specific examples, which are presented only to assist in understanding the method and its core concepts. It should be noted that, for those skilled in the art, it is possible to make various improvements and modifications to the present invention without departing from the principle of the present invention, and those improvements and modifications also fall within the scope of the claims of the present invention.

Claims (8)

1. A method for judging emergency operation regulations of a nuclear power station is characterized by comprising the following steps:
collecting the on-site state information of the nuclear power station, and accepting the checking information input by a user;
determining an execution path of procedure selection nodes in a digital model corresponding to the procedure flow chart according to the state information and the check information; the procedure selection node comprises a state node and a check node; the digital model is a cyclic tree structure and comprises a starting node, a plurality of procedure selecting nodes and a plurality of procedure page nodes;
starting a starting node of the digital model, executing a procedure selection node, and acquiring information of a procedure page to be executed.
2. The method of claim 1, further comprising:
and updating the state information and the check information input by the user at intervals of preset time, restarting a starting node of the digital model, executing a procedure selection node, and acquiring new procedure page information to be executed.
3. The method of claim 2, wherein determining an execution path of a procedure selection node corresponding to a procedure flow graph according to the state information and the check information comprises:
judging whether the state information meets the node condition of the state node, if so, determining the value of the state node to be 1, and executing a path corresponding to the value 1; if not, determining that the numerical value of the state node is 0, and executing a path corresponding to the numerical value 0;
judging whether the checking information meets the node condition of the checking node, if so, determining the value of the checking node to be 1, and executing a path corresponding to the value 1; if not, determining that the value of the check node is 0, and executing a path corresponding to the value 0.
4. The method of any one of claims 1 to 3, further comprising, after the obtaining procedure page information to be executed:
and displaying the procedure page information to be executed and the fault state corresponding to the procedure page information.
5. A device for judging emergency operation procedures of nuclear power plants, which is used for implementing the method of any one of claims 1 to 4, and comprises:
the acquisition module is used for acquiring the on-site state information of the nuclear power station and receiving the checking information input by a user;
a path determining module, configured to determine, according to the state information and the check information, an execution path of a procedure selection node in a digital model corresponding to the procedure flowchart; the procedure selection node comprises a state node and a check node; the digital model is a cyclic tree structure and comprises a starting node, a plurality of procedure selecting nodes and a plurality of procedure page nodes;
and the starting module is used for starting the starting node of the digital model, executing the procedure selection node and acquiring the information of the procedure page to be executed.
6. The apparatus of claim 5, further comprising:
and the updating module is used for updating the state information and the check information input by the user at intervals of preset time, restarting a starting node of the digital model, executing a procedure selection node and acquiring new procedure page information to be executed.
7. The apparatus of claim 6, wherein the determine path module comprises:
the first judging unit is used for judging whether the state information meets the node condition of the state node, if so, the value of the state node is determined to be 1, and a path corresponding to the value 1 is executed; if not, determining that the numerical value of the state node is 0, and executing a path corresponding to the numerical value 0;
the second judging unit is used for judging whether the checking information meets the node condition of the checking node, if so, the value of the checking node is determined to be 1, and the path corresponding to the value 1 is executed; if not, determining that the value of the check node is 0, and executing a path corresponding to the value 0.
8. The apparatus of any one of claims 5 to 7, further comprising:
and the display module is used for displaying the procedure page information to be executed and the fault state corresponding to the procedure page information.
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* Cited by examiner, † Cited by third party
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CN113744909A (en) * 2021-09-03 2021-12-03 中广核工程有限公司 Digital procedure pushing method and device for nuclear power plant and computer equipment
CN113744909B (en) * 2021-09-03 2023-12-01 中广核工程有限公司 Nuclear power plant digital procedure pushing method and device and computer equipment

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