CN110110999A - System event HRA evaluation method, device, equipment and medium in master-control room of nuclear power plant - Google Patents
System event HRA evaluation method, device, equipment and medium in master-control room of nuclear power plant Download PDFInfo
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Abstract
This application discloses system event HRA evaluation method, device, equipment and media in a kind of master-control room of nuclear power plant, this method comprises: identifying the cut set sequence for causing human-equation error event；Determine the human behavior unit in cut set sequence；Acquire personnel's operation information corresponding with human behavior unit；According to when ordered pair personnel's operation information in manipulative behavior information relevant to human-equation error event record, obtain manipulating fault behavior relevant information accordingly；The manipulative behavior of operator is analyzed using manipulation fault behavior relevant information, to obtain the first behavior formation factor relevant to event occurrence scene and recognize relevant second behavior formation factor with personnel；Using the first behavior formation factor and the second behavior formation factor, HRA evaluation is carried out to system event in master-control room of nuclear power plant, is obtained accordingly for characterizing the HRA analysis result of nuclear power plant's operating status.The application can be realized the more objective and accurate HRA evaluation to system event in master-control room of nuclear power plant.
Description
Technical field
This application involves technical field of nuclear power, in particular to system event human factors analysis point in a kind of master-control room of nuclear power plant
Analyse (Human Reliability Analysis, HRA) evaluation method, device, equipment and medium.
Background technique
Nuclear power is all applied, before wide application as a kind of clean energy resource in many countries and regions in the whole world
Scape.
It is asked however, nuclear power plant during producing nuclear power, needs to face nuclear safety not available for other generation modes
Topic.For this purpose, to the operational process of nuclear power plant system carry out evaluation analysis be in order to determine nuclear power plant's operation whether An Quan one
Important link, and how to realize be that current people pay special attention to the more objective and accurate evaluation analysis of nuclear power plant system one
A problem.
Summary of the invention
In view of this, the application's is designed to provide system event HRA evaluation method in a kind of master-control room of nuclear power plant, dress
It sets, equipment and medium, can be realized the more objective and accurate HRA evaluation to system event in master-control room of nuclear power plant.It is specific
Scheme is as follows:
In a first aspect, this application discloses system event HRA evaluation methods in a kind of master-control room of nuclear power plant, comprising:
Using the human-equation error event in the event tree of system event in master-control room of nuclear power plant as top event, drawn with identifying
The cut set sequence of the human-equation error event is played, includes at least one human behavior unit in the cut set sequence；
Determine the human behavior unit in the cut set sequence；
Acquire corresponding with human behavior unit personnel's operation information, personnel's operation information include operator into
The operation behavior information of row manipulative behavior；
According to when ordered pair described in personnel's operation information manipulative behavior information relevant to the human-equation error event carry out
Record, obtains manipulating fault behavior relevant information accordingly；
The manipulative behavior of the operator is analyzed using the manipulation fault behavior relevant information, to obtain
First behavior formation factor and the second behavior formation factor, the thing of first behavior formation factor and the human-equation error event
Part occurrence scene is related, and second behavior formation factor is related to the personnel of operator cognition
Using first behavior formation factor and second behavior formation factor, to being in the master-control room of nuclear power plant
System event carries out HRA evaluation, obtains accordingly for characterizing the HRA analysis result of nuclear power plant's operating status.
Optionally, it is described according to when ordered pair described in personnel's operation information manipulation relevant to the human-equation error event go
It is recorded for information, comprising:
According to timing respectively to carelessness type relevant to the human-equation error event in personnel's operation information fault and
The operation behavior information of execution type fault is recorded.
Optionally, it is described according to when ordered pair described in personnel's operation information manipulation relevant to the human-equation error event go
It is recorded for information, comprising:
By the way of charting, and according to when ordered pair described in personnel's operation information with the human-equation error event phase
The manipulative behavior information of pass is recorded.
Optionally, first behavior formation factor, including by behavior be intended to caused by be intended to behavior formation factor and
The environmental behaviour as caused by current environment forms the factor；
Second behavior formation factor, including the effect behavior formation factor as caused by recency effect and won by frequency
Game behavior caused by playing chess forms the factor.
Second aspect, this application discloses system event HRA evaluating apparatus in a kind of master-control room of nuclear power plant, comprising:
Cut set recognition sequence module, for by the human-equation error event in the event tree of system event in master-control room of nuclear power plant
It include at least one in the cut set sequence to identify the cut set sequence for causing the human-equation error event as top event
Human behavior unit；
Behavior unit determining module, for determining the human behavior unit in the cut set sequence；
Operation information acquisition module, for acquiring personnel's operation information corresponding with the human behavior unit, the people
Member's operation information includes the operation behavior information that operator carries out manipulative behavior；
Fault behavior relevant information logging modle, for according to when ordered pair described in personnel's operation information with the people because losing
The relevant operation behavior information of part of causing delay is recorded, and obtains manipulating fault behavior relevant information accordingly；
Manipulative behavior analysis module, for the manipulation row using the manipulation fault behavior relevant information to the operator
To be analyzed, to obtain the first behavior formation factor and the second behavior formation factor, first behavior formation factor and institute
The event occurrence scene for stating human-equation error event is related, and second behavior formation factor and the personnel of the operator recognize phase
It closes；
HRA evaluation module, for utilizing first behavior formation factor and second behavior formation factor, to described
System event carries out HRA evaluation in master-control room of nuclear power plant, obtains accordingly for characterizing the HRA analysis knot of nuclear power plant's operating status
Fruit.
Optionally, the fault behavior relevant information logging modle is specifically used for respectively grasping the personnel according to timing
The operation behavior information of carelessness type fault relevant to the human-equation error event and execution type fault is recorded in vertical information.
Optionally, the fault behavior relevant information logging modle, specifically for by the way of charting, and according to
When ordered pair described in personnel's operation information the relevant information of relevant to human-equation error event human-equation error record.
Optionally, first behavior formation factor, including by behavior be intended to caused by be intended to behavior formation factor and
The environmental behaviour as caused by current environment forms the factor；
Second behavior formation factor, including the effect behavior formation factor as caused by recency effect and won by frequency
Game behavior caused by playing chess forms the factor.
The third aspect, this application discloses system event HRA valuator devices in a kind of master-control room of nuclear power plant, comprising:
Memory, for storing computer program；
Processor is to realize in master-control room of nuclear power plant disclosed in previous embodiment for executing the computer program
System event HRA evaluation method.
Fourth aspect, this application discloses a kind of computer readable storage mediums, for storing computer program, wherein
System event HRA evaluation in master-control room of nuclear power plant disclosed in previous embodiment is realized when the computer program is executed by processor
Method.
As it can be seen that the application is first using the human-equation error event in the time tree of system event in master-control room of nuclear power plant as event
Then the top event of tree determines the personnel in cut set sequence to determine to may cause the cut set sequence of human-equation error event
Behavior unit, and acquire corresponding with human behavior unit personnel's operation information, then in above-noted persons' operation information with
The relevant information of human error records, and obtains manipulation fault behavior relevant information, and then utilize above-mentioned manipulation fault behavior
Relevant information analyzes the manipulative behavior of operator, obtains the first behavior formation factor relevant to event occurrence scene and and personnel
Relevant second behavior formation factor is recognized, finally using above two behavior formation factor to system thing in master-control room of nuclear power plant
Part carries out HRA analysis.It can be seen that the application, which is equivalent to, first determines may cause according to the initial symptoms of accident people because losing
It causes delay the behavior unit of part, then acquires the corresponding personnel's operation information of above-mentioned behavior unit, it is this to be equivalent to using task point
Analysis method carrys out the way of collector's operation information, enables to collected personnel's operation information compared to existing based on the time
The collected operation information of window is more in line with the actual conditions that operator in master control room manipulates, and is conducive to improve subsequent HRA and comment
The objectivity and accuracy of valence result, in addition, since the application is making mistakes behavior relevant information to operator using above-mentioned manipulation
Manipulative behavior when being analyzed, be recognize in two dimensions to be analyzed from event occurrence scene and personnel, thus
Obtain behavior formation factor relevant to event occurrence scene and recognize relevant behavior formation factor with personnel, it is subsequent in this way
It is above-mentioned relevant to event occurrence scene in addition to can use when carrying out HRA evaluation to the system event in master-control room of nuclear power plant
Behavior formation factor can also utilize above-mentioned behavior formation factor relevant to personnel's cognition, can make final HRA in this way
Evaluation result can be more objective and accurate, is more in line with the actual operating state of nuclear power plant, to be conducive to improve nuclear power plant
Safety.To sum up, the application can be realized the more objective and accurate HRA evaluation to system event in master-control room of nuclear power plant.
Detailed description of the invention
In order to illustrate the technical solutions in the embodiments of the present application or in the prior art more clearly, to embodiment or will show below
There is attached drawing needed in technical description to be briefly described, it should be apparent that, the accompanying drawings in the following description is only this
The embodiment of application for those of ordinary skill in the art without creative efforts, can also basis
The attached drawing of offer obtains other attached drawings.
Fig. 1 is system event HRA evaluation method flow chart in a kind of master-control room of nuclear power plant disclosed in the present application；
Fig. 2 is system event HRA evaluation method flow chart in a kind of specific master-control room of nuclear power plant disclosed in the present application；
Fig. 3 is system event HRA evaluating apparatus structural schematic diagram in a kind of master-control room of nuclear power plant disclosed in the present application.
Specific embodiment
Below in conjunction with the attached drawing in the embodiment of the present application, technical solutions in the embodiments of the present application carries out clear, complete
Site preparation description, it is clear that described embodiments are only a part of embodiments of the present application, instead of all the embodiments.It is based on
Embodiment in the application, it is obtained by those of ordinary skill in the art without making creative efforts every other
Embodiment shall fall in the protection scope of this application.
The concrete application scene for introducing system event HRA evaluation method in the application master-control room of nuclear power plant first, in nuclear power
In the operation of factory, nuclear power plant's probabilistic risk assessment (Probabilistic Risk Assessment, PRA) be to design or
The safe condition of running nuclear power plant makes a kind of systematic method of evaluation, the object of PRA be the system for running nuclear power plant,
Personnel and man-machine interface.Since nuclear power plant is run by personnel, then judging the system occurred in the system of nuclear power plant
The standard of the success of event or failure is exactly: human behavior whether meet or with it is much a possibility that meet system event
Success criterion.
Human behavior is divided into the human behavior under nuclear power plant's normal operating condition and the human behavior under abnormality.And it is different
Human behavior under normal state is divided into two kinds of situations again, the human behavior after accident occurs one is nuclear power plant, another kind is
Human behavior after nuclear power plant's transient state.The method that operating process and correctness to human behavior are analyzed is exactly HRA method.
But existing HRA method either uses Analysis of Errors (the A Technique for Human Event of people
Analysis, ATHEANA) method or human cognitive fail-safe analysis (Human Cognitive Reliability, HCR) method,
When starting due to accident, it can not show completely, operator can not predict and determine be which kind of accident occurs actually,
These cannot reflect the actual conditions of operator's manipulation using the method for time window completely.
Therefore, in order to solve problem above existing for existing HRA method, research of the application in existing HRA method
On the basis of, construct the research method of a kind of systematization analyzed human behavior under abnormality.Especially by following
Each embodiment says system event HRA evaluation method, device, equipment and medium in the master-control room of nuclear power plant of the application respectively
It is bright.
Shown in Figure 1, the embodiment of the present application discloses system event HRA evaluation method in a kind of master-control room of nuclear power plant,
Include:
Step S11: using the human-equation error event in the event tree of system event in master-control room of nuclear power plant as top event, with
It identifies the cut set sequence for causing the human-equation error event, includes at least one human behavior unit in the cut set sequence.
Step S12: the human behavior unit in the cut set sequence is determined.
Step S13: acquisition personnel's operation information corresponding with the human behavior unit, personnel's operation information include
The operation behavior information of operator's progress manipulative behavior.
For example, the corresponding commanding apparatus information of each personnel's behavior unit can be acquired, manipulative behavior information, can be manipulated
Limit value, position, the operator's performance etc. of equipment instruction.
Step S14: according to when ordered pair described in operation behavior relevant to the human-equation error event in personnel's operation information
Information is recorded, and obtains manipulating fault behavior relevant information accordingly.
In the present embodiment, after collecting various personnel's operation informations, it is also necessary to manipulate and believe to these personnel
Operation behavior information relevant to human-equation error event is recorded in breath, and can be in such a way that timing records come sequentially
Record various information relevant to human error.
In the present embodiment, human error can specifically include the fault of carelessness type and execution type fault, that is, the present embodiment can
With the behaviour to make mistakes respectively to carelessness type relevant to human-equation error event in personnel's operation information fault and execution type according to timing
It is recorded as behavioural information.
In addition, the present embodiment can also by the way of charting, and according to when ordered pair personnel's operation information in people
Because the relevant operation behavior information of fault event is recorded.
Step S15: analyzing the manipulative behavior of the operator using the manipulation fault behavior relevant information, with
Obtain the first behavior formation factor and the second behavior formation factor, first behavior formation factor and the human-equation error event
Event occurrence scene it is related, second behavior formation factor is related to the personnel of operator cognition.
In the present embodiment, the manipulative behavior of operator is analyzed using above-mentioned manipulation fault behavior relevant information
When, it is to recognize the two angles from event occurrence scene and personnel to be analyzed, thus obtains and event occurrence scene phase
The first behavior formation factor and the second behavior formation factor relevant to personnel's cognition closed.That is, the present embodiment is specifically base
The manipulative behavior of operator is analyzed in scene mode trigger and Cognitive Mode trigger.
Further, first behavior formation factor in the present embodiment can specifically include and be caused by behavior intention
Intention behavior formation factor (i.e. PSF, Performance Shaping Factor) and the environment as caused by current environment
Behavior formation factor；
In addition, second behavior formation factor in the present embodiment, can specifically include the effect as caused by recency effect
Behavior formation factor and the game behavior as caused by frequency game is answered to form the factor.
Wherein, recency effect considers personnel's everyday practice PSF, and the training time is closer, and the specific value of corresponding PSF is also got over
Height, and frequency game then considers the horizontal PSF of training of operator, training is horizontal higher, and the triggering of frequency game schema of cognition can
Energy property is higher.
Step S16: first behavior formation factor and second behavior formation factor are utilized, to the nuclear power factory owner
It controls indoor heating system event and carries out HRA evaluation, obtain accordingly for characterizing the HRA analysis result of nuclear power plant's operating status.
That is, the present embodiment is to utilize behavior formation factor relevant to event occurrence scene and recognize with personnel relevant
Behavior formation factor to carry out HRA evaluation to system event in nuclear power plant's main control, so that final HRA evaluation result
Can be more objective and accurate, it is more in line with the actual operating state of nuclear power plant, to be conducive to improve the safety of nuclear power plant.
To sum up, the embodiment of the present application, which is equivalent to, first determines may cause according to the initial symptoms of accident people because losing
It causes delay the behavior unit of part, then acquires the corresponding personnel's operation information of above-mentioned behavior unit, it is this to be equivalent to using task point
Analysis method carrys out the way of collector's operation information, enables to collected personnel's operation information compared to existing based on the time
The collected operation information of window is more in line with the actual conditions that operator in master control room manipulates, and is conducive to improve subsequent HRA and comment
The objectivity and accuracy of valence result, in addition, since the embodiment of the present application is utilizing above-mentioned manipulation fault behavior relevant information pair
It is to recognize in two dimensions to analyze from event occurrence scene and personnel when the manipulative behavior of operator is analyzed
, thus obtain behavior formation factor relevant to event occurrence scene and recognize relevant behavior formation factor with personnel, this
Sample is subsequent when carrying out HRA evaluation to the system event in master-control room of nuclear power plant, and field occurs in addition to can use above-mentioned and event
The relevant behavior formation factor of scape can also utilize above-mentioned behavior formation factor relevant to personnel's cognition, can make in this way
Final HRA evaluation result can be more objective and accurate, is more in line with the actual operating state of nuclear power plant, to be conducive to improve
The safety of nuclear power plant.To sum up, the embodiment of the present application can be realized the more objective standard to system event in master-control room of nuclear power plant
True HRA evaluation.
Shown in Figure 2, the embodiment of the present application discloses system event HRA evaluation in a kind of specific master-control room of nuclear power plant
Method, comprising:
Step S21: using the human-equation error event in the event tree of system event in master-control room of nuclear power plant as top event, with
It identifies the cut set sequence for causing the human-equation error event, includes at least one human behavior unit in the cut set sequence.
Step S22: the human behavior unit in the cut set sequence is determined.
Step S23: acquisition personnel's operation information corresponding with the human behavior unit, personnel's operation information include
The operation behavior information of operator's progress manipulative behavior.
Step S24: by the way of charting, and according to timing respectively in personnel's operation information with the people
Because the operation behavior information of the relevant carelessness type fault of fault event and execution type fault is recorded, obtains manipulating accordingly and lose
Accidentally behavior relevant information.
Step S25: analyzing the manipulative behavior of the operator using the manipulation fault behavior relevant information, with
Obtain the first behavior formation factor and the second behavior formation factor, first behavior formation factor and the human-equation error event
Event occurrence scene it is related, second behavior formation factor is related to the personnel of operator cognition.
Step S26: first behavior formation factor and second behavior formation factor are utilized, to the nuclear power factory owner
It controls indoor heating system event and carries out HRA evaluation, obtain accordingly for characterizing the HRA analysis result of nuclear power plant's operating status.
Shown in Figure 3, the embodiment of the present application also discloses system event HRA evaluation dress in a kind of master-control room of nuclear power plant
It sets, comprising:
Cut set recognition sequence module 11, for by the human-equation error thing in the event tree of system event in master-control room of nuclear power plant
Part is as top event, includes at least one in the cut set sequence to identify the cut set sequence for causing the human-equation error event
A personnel's behavior unit；
Behavior unit determining module 12, for determining the human behavior unit in the cut set sequence；
Operation information acquisition module 13, it is described for acquiring personnel's operation information corresponding with the human behavior unit
Personnel's operation information includes the operation behavior information that operator carries out manipulative behavior；
Fault behavior relevant information logging modle 14, for according to when ordered pair described in personnel's operation information with the people because
The relevant operation behavior information of fault event is recorded, and obtains manipulating fault behavior relevant information accordingly；
Manipulative behavior analysis module 15, for the manipulation using the manipulation fault behavior relevant information to the operator
Behavior is analyzed, to obtain the first behavior formation factor and the second behavior formation factor, first behavior formation factor with
The event occurrence scene of the human-equation error event is related, and the personnel of second behavior formation factor and the operator recognize
It is related；
HRA evaluation module 16, for utilizing first behavior formation factor and second behavior formation factor, to institute
It states system event in master-control room of nuclear power plant and carries out HRA evaluation, obtain accordingly for characterizing the HRA analysis of nuclear power plant's operating status
As a result.
To sum up, the embodiment of the present application, which is equivalent to, first determines may cause according to the initial symptoms of accident people because losing
It causes delay the behavior unit of part, then acquires the corresponding personnel's operation information of above-mentioned behavior unit, it is this to be equivalent to using task point
Analysis method carrys out the way of collector's operation information, enables to collected personnel's operation information compared to existing based on the time
The collected operation information of window is more in line with the actual conditions that operator in master control room manipulates, and is conducive to improve subsequent HRA and comment
The objectivity and accuracy of valence result, in addition, since the embodiment of the present application is utilizing above-mentioned manipulation fault behavior relevant information pair
It is to recognize in two dimensions to analyze from event occurrence scene and personnel when the manipulative behavior of operator is analyzed
, thus obtain behavior formation factor relevant to event occurrence scene and recognize relevant behavior formation factor with personnel, this
Sample is subsequent when carrying out HRA evaluation to the system event in master-control room of nuclear power plant, and field occurs in addition to can use above-mentioned and event
The relevant behavior formation factor of scape can also utilize above-mentioned behavior formation factor relevant to personnel's cognition, can make in this way
Final HRA evaluation result can be more objective and accurate, is more in line with the actual operating state of nuclear power plant, to be conducive to improve
The safety of nuclear power plant.To sum up, the embodiment of the present application can be realized the more objective standard to system event in master-control room of nuclear power plant
True HRA evaluation.
Further, in the present embodiment, the fault behavior relevant information logging modle, specifically for distinguishing according to timing
To the operation behavior of carelessness type relevant to the human-equation error event in personnel's operation information fault and execution type fault
Information is recorded.
In addition, in the present embodiment, the fault behavior relevant information logging modle, specifically for the side using charting
Formula, and according to when ordered pair described in personnel's operation information operation behavior information relevant to the human-equation error event remember
Record.
Further, in the present embodiment, first behavior formation factor, including caused intention behavior is intended to by behavior
It forms the factor and the environmental behaviour as caused by current environment forms the factor；
Second behavior formation factor, including the effect behavior formation factor as caused by recency effect and won by frequency
Game behavior caused by playing chess forms the factor.
Further, disclosed herein as well is system event HRA valuator devices in a kind of master-control room of nuclear power plant, comprising:
Memory, for storing computer program；
Processor, for executing the computer program, to realize, system event HRA is commented in master-control room of nuclear power plant above-mentioned
Valence method.
Further, disclosed herein as well is a kind of computer readable storage mediums, for storing computer program,
In, the computer program realizes system event HRA evaluation method in master-control room of nuclear power plant above-mentioned when being executed by processor.
It wherein, can be with reference to corresponding contents disclosed in previous embodiment, herein not about the specific steps of the above method
It is repeated again.
Each embodiment in this specification is described in a progressive manner, the highlights of each of the examples are with it is other
The difference of embodiment, same or similar part may refer to each other between each embodiment.For being filled disclosed in embodiment
For setting, since it is corresponded to the methods disclosed in the examples, so being described relatively simple, related place is referring to method part
Explanation.
The step of method described in conjunction with the examples disclosed in this document or algorithm, can directly be held with hardware, processor
The combination of capable software module or the two is implemented.Software module can be placed in random access memory (RAM), memory, read-only deposit
Reservoir (ROM), electrically programmable ROM, electrically erasable ROM, register, hard disk, moveable magnetic disc, CD-ROM or technology
In any other form of storage medium well known in field.
Above to system event HRA evaluation method in a kind of master-control room of nuclear power plant provided herein, device, equipment and
Medium is described in detail, and specific examples are used herein to illustrate the principle and implementation manner of the present application, with
The explanation of upper embodiment is merely used to help understand the present processes and its core concept；Meanwhile for the general of this field
Technical staff, according to the thought of the application, there will be changes in the specific implementation manner and application range, in conclusion
The contents of this specification should not be construed as limiting the present application.
Claims (10)
1. system event HRA evaluation method in a kind of master-control room of nuclear power plant characterized by comprising
Using the human-equation error event in the event tree of system event in master-control room of nuclear power plant as top event, cause institute to identify
The cut set sequence of human-equation error event is stated, includes at least one human behavior unit in the cut set sequence；
Determine the human behavior unit in the cut set sequence；
Personnel's operation information corresponding with the human behavior unit is acquired, personnel's operation information includes that operator grasps
The operation behavior information that stringer is；
According to when ordered pair described in personnel's operation information manipulative behavior information relevant to the human-equation error event record,
It obtains manipulating fault behavior relevant information accordingly；
The manipulative behavior of the operator is analyzed using the manipulation fault behavior relevant information, to obtain first
The event of behavior formation factor and the second behavior formation factor, first behavior formation factor and the human-equation error event is sent out
Raw scene is related, and second behavior formation factor is related to the personnel of operator cognition；
Using first behavior formation factor and second behavior formation factor, to system thing in the master-control room of nuclear power plant
Part carries out HRA evaluation, obtains accordingly for characterizing the HRA analysis result of nuclear power plant's operating status.
2. system event HRA evaluation method in master-control room of nuclear power plant according to claim 1, which is characterized in that described to press
According to when ordered pair described in personnel's operation information manipulative behavior information relevant to the human-equation error event record, comprising:
Carelessness type relevant to the human-equation error event in personnel's operation information is made mistakes and executed respectively according to timing
The operation behavior information of type fault is recorded.
3. system event HRA evaluation method in master-control room of nuclear power plant according to claim 1, which is characterized in that described to press
According to when ordered pair described in personnel's operation information operation behavior information relevant to the human-equation error event record, comprising:
By the way of charting, and according to when ordered pair described in personnel's operation information it is relevant to the human-equation error event
Manipulative behavior information is recorded.
4. system event HRA evaluation method, feature exist in master-control room of nuclear power plant according to any one of claims 1 to 3
In,
First behavior formation factor, including be intended to behavior formation factor caused by being intended to by behavior and drawn by current environment
The environmental behaviour risen forms the factor；
Second behavior formation factor, including the effect behavior formation factor as caused by recency effect and drawn by frequency game
The game behavior risen forms the factor.
5. system event HRA evaluating apparatus in a kind of master-control room of nuclear power plant characterized by comprising
Cut set recognition sequence module, for using the human-equation error event in the event tree of system event in master-control room of nuclear power plant as
Top event includes at least one personnel in the cut set sequence to identify the cut set sequence for causing the human-equation error event
Behavior unit；
Behavior unit determining module, for determining the human behavior unit in the cut set sequence；
Operation information acquisition module, for acquiring personnel's operation information corresponding with the human behavior unit, the personnel behaviour
Vertical information includes the operation behavior information that operator carries out manipulative behavior；
Fault behavior relevant information logging modle, for according to when ordered pair described in personnel's operation information with the human-equation error thing
The relevant operation behavior information of part is recorded, and obtains manipulating fault behavior relevant information accordingly；
Manipulative behavior analysis module, for using the manipulation fault behavior relevant information to the manipulative behavior of the operator into
Row analysis, to obtain the first behavior formation factor and the second behavior formation factor, first behavior formation factor and the people
Because the event occurrence scene of fault event is related, second behavior formation factor is related to the personnel of operator cognition；
HRA evaluation module, for utilizing first behavior formation factor and second behavior formation factor, to the nuclear power
Factory owner controls indoor heating system event and carries out HRA evaluation, obtains accordingly for characterizing the HRA analysis result of nuclear power plant's operating status.
6. system event HRA evaluating apparatus in master-control room of nuclear power plant according to claim 5, which is characterized in that
The fault behavior relevant information logging modle, be specifically used for according to timing respectively in personnel's operation information with institute
The operation behavior information for stating the relevant carelessness type fault of human-equation error event and execution type fault is recorded.
7. system event HRA evaluating apparatus in master-control room of nuclear power plant according to claim 5, which is characterized in that
The fault behavior relevant information logging modle, specifically for by the way of charting, and according to when ordered pair described in
Operation behavior information relevant to the human-equation error event records in personnel's operation information.
8. according to system event HRA evaluating apparatus in the described in any item master-control room of nuclear power plant of claim 5 to 7, feature exists
In,
First behavior formation factor, including be intended to behavior formation factor caused by being intended to by behavior and drawn by current environment
The environmental behaviour risen forms the factor；
Second behavior formation factor, including the effect behavior formation factor as caused by recency effect and drawn by frequency game
The game behavior risen forms the factor.
9. system event HRA valuator device in a kind of master-control room of nuclear power plant characterized by comprising
Memory, for storing computer program；
Processor, for executing the computer program, to realize such as the described in any item nuclear power plant's master controls of Claims 1-4
Indoor heating system event HRA evaluation method.
10. a kind of computer readable storage medium, which is characterized in that for storing computer program, wherein the computer journey
It is realized when sequence is executed by processor such as the evaluation side system event HRA in the described in any item master-control room of nuclear power plant of Claims 1-4
Method.
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Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN111950359A (en) * | 2020-07-06 | 2020-11-17 | 核动力运行研究所 | Intelligent system and method for preventing human errors of nuclear power plant |
| CN112598223A (en) * | 2020-12-03 | 2021-04-02 | 中广核工程有限公司 | Nuclear power state oriented law accident rule completeness inspection method and system, electronic equipment and storage medium |
Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US20110258021A1 (en) * | 2010-04-19 | 2011-10-20 | Mumaw Randall Jay | Human reliability assessment tool supporting safety issue analysis and management |
| CN103198231A (en) * | 2013-04-23 | 2013-07-10 | 湖南工学院 | Method and system for judging reliability of man-machine interfaces of DCS (digital control system) by means of HRA (human reliability analysis) |
| CN109034636A (en) * | 2018-08-07 | 2018-12-18 | 湖南工学院 | Power changes continuously and healthily lower-pilot person's human reliability analysis method and apparatus |
| CN109299868A (en) * | 2018-09-14 | 2019-02-01 | 湖南工学院 | Multiunit nuclear power plant dynamic human reliability analysis method and apparatus |
| CN109492906A (en) * | 2018-11-08 | 2019-03-19 | 南华大学 | Response executes reliability estimation method, device and equipment |
-
2019
- 2019-05-06 CN CN201910371575.7A patent/CN110110999A/en active Pending
Patent Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US20110258021A1 (en) * | 2010-04-19 | 2011-10-20 | Mumaw Randall Jay | Human reliability assessment tool supporting safety issue analysis and management |
| CN103198231A (en) * | 2013-04-23 | 2013-07-10 | 湖南工学院 | Method and system for judging reliability of man-machine interfaces of DCS (digital control system) by means of HRA (human reliability analysis) |
| CN109034636A (en) * | 2018-08-07 | 2018-12-18 | 湖南工学院 | Power changes continuously and healthily lower-pilot person's human reliability analysis method and apparatus |
| CN109299868A (en) * | 2018-09-14 | 2019-02-01 | 湖南工学院 | Multiunit nuclear power plant dynamic human reliability analysis method and apparatus |
| CN109492906A (en) * | 2018-11-08 | 2019-03-19 | 南华大学 | Response executes reliability estimation method, device and equipment |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN111950359A (en) * | 2020-07-06 | 2020-11-17 | 核动力运行研究所 | Intelligent system and method for preventing human errors of nuclear power plant |
| CN112598223A (en) * | 2020-12-03 | 2021-04-02 | 中广核工程有限公司 | Nuclear power state oriented law accident rule completeness inspection method and system, electronic equipment and storage medium |
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