KR101541150B1 - Common cause failure parameter evaluation system and method for nuclear power plant equipment - Google Patents

Abstract

The present invention relates to a common cause failure parameter evaluation system and a method for nuclear power plant equipment. The purpose of the prevent invention is to provide a system which evaluates a parameter by a parameter analysis method and evaluates a common cause failure parameter by considering the test and maintenance property of a device, and evaluates the common cause failure parameter of the last data source. For this purposes, the present invention includes a parameter data part which stores parameter data; a selection part which selects a kind of a common cause failure evaluation device, selects a failure mode and a corresponding system according to the selected device, and selects the number of common cause failure parameter evaluation device groups; and a parameter evaluation part which evaluates parameter data received through the parameter data part and a common cause failure parameter based on information received through an input part.

Description

{Common cause failure parameter evaluation system and method for nuclear power plant equipment}

The present invention relates to a common cause failure parameter input system and method of nuclear power plant equipment, and more particularly, to a system and method for common cause failure parameter input of a nuclear power plant equipment, A parameter evaluating method, and a parameter evaluating method according to a parameter analyzing method, and a method thereof.

A probabilistic safety assessment (PSA) is used as a comprehensive safety evaluation method for nuclear power plants and a failure of the equipment in the fault tree that evaluates the inability to use the equipment as a common method for evaluating the failure of the equipment As a factor to be evaluated.

In relation to the evaluation of common cause failure parameters, 'development of common cause failure parameter estimation tool from failure experience data' (hereinafter referred to as 'prior literature') and many others are filed and disclosed.

However, in the past including the precedent documents, the general data source being applied as a parameter of the common cause failure is mainly based on the experience data of the 1970s, and the quality problem of the common cause fault evaluation is raised. It is not applied to the cause failure analysis. In addition, the common cause of equipment failure is rare event, lack of experience data, and in Korea, there is no data to evaluate the parameters of common cause failure.

Development of a common cause failure parameter estimation tool from the failure experience data Choi, YK, Kim, Tae-Woon, Park, ChangGyu,

SUMMARY OF THE INVENTION The present invention has been made in view of the above problems, and it is an object of the present invention to provide a method and apparatus for evaluating common cause failure parameters of the latest data sources, evaluating common cause failure parameters by considering the test and maintenance characteristics of the apparatus, A system and method for evaluating parameters are provided.

In order to accomplish the above object, the present invention provides a common cause failure parameter evaluation system for a nuclear power plant, comprising: a parameter data unit storing parameter data; A selection unit that selects a common cause failure evaluation target device type, selects a failure mode and a corresponding system according to the selected device type, and selects the group number of the common cause failure evaluation target device group; A parameter evaluating unit for evaluating a common cause failure parameter based on the parameter data received through the parameter data unit and the information received through the input unit; .

Further, the parameter data includes a common cause failure common data source including operation data of US nuclear power plants.

The parameter evaluating unit receives the parameter distribution information of the general data source from the parameter data unit, and calculates the common cause failure evaluation target device type, the failure mode, the system, the number of groups, An input information receiving module for receiving the cause failure data information; A test / maintenance characteristic evaluation module for evaluating common cause failure parameters for sequential testing or nonsequential testing of common cause failure evaluation devices based on information received through the input information receiving module; An analysis method evaluation module for evaluating parameters using an MLA (Multiple Greek Letter) method applied in the PSA model of domestic nuclear power plants and a suitable alpha factor method in terms of statistical processing; A fault tree reflection factor evaluation module for evaluating a common cause fault factor applied to the fault tree of the PSA model; And an output module outputting an evaluation result; And a control unit.

According to another aspect of the present invention, there is provided a method for evaluating common cause failure parameters of a nuclear power plant equipment, comprising the steps of: (a) selecting a common cause failure evaluation target equipment type; (b) selecting a failure mode and a corresponding system according to the selected device type; (c) selecting the number of groups of the common cause failure evaluation target device group by the selection unit; (d) a parameter evaluation unit receiving parameter distribution information of a general data source from the parameter data unit; (e) receiving a common cause failure evaluation target device type, a failure mode, a system, a group number, and a failure factor data information that are intrinsic common cause cause intrinsic to be evaluated from the parameter evaluation unit selection unit; (f) evaluating a common cause failure parameter for sequential or nonsequential testing of the common cause failure evaluation device based on the information received through the steps (d) to (e) ; (g) evaluating parameters using the MGL (Multiple Greek Letter) method and the advantageous alpha factor method in terms of statistical processing applied by the parameter evaluating unit in the PSA model of the domestic nuclear power plant; And (h) evaluating a common cause failure factor to be directly applied to the failure rate / failure probability evaluation to be reflected in the failure tree of the PSA model, and outputting an evaluation result; .

According to the present invention as described above, it is possible to improve the quality of the common cause failure evaluation.

BRIEF DESCRIPTION OF THE DRAWINGS FIG. 1 is a block diagram conceptually showing a common cause failure parameter evaluation system of a nuclear power plant according to the present invention; FIG.
2 is an overall flowchart of a method for evaluating common cause failure parameters of a nuclear power plant equipment according to the present invention.

Specific features and advantages of the present invention will become more apparent from the following detailed description based on the accompanying drawings. It is to be noted that the detailed description of known functions and constructions related to the present invention is omitted when it is determined that the gist of the present invention may be unnecessarily blurred.

DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS The present invention will now be described in detail with reference to the accompanying drawings.

A common cause failure parameter evaluation system and method of a nuclear power plant equipment according to the present invention will be described with reference to FIG. 1 to FIG.

FIG. 1 is an overall schematic diagram illustrating a common cause failure parameter evaluation system (S) of a nuclear power plant equipment according to the present invention. As shown in FIG. 1, the parameter data unit 100, the selection unit 200, And a variable evaluation unit (300).

The parameter data section 100 stores parameter data.

Based on the experience of the US Nuclear Power Plant, the parameter data is based on the common data source, which is a common cause of failure periodically issued by the US nuclear regulator, US NRC. Based on the experience of the PWRC operator group, Evaluated Common Causes Failure Can include generic data sources.

That is, common data sources including common source failure data including operation data of US Nuclear Power Plants and common cause failure general data sources evaluated based on PWR operation data can be used.

Here, other generic data sources can be added, and the generic data source can be periodically revised.

The selection unit 200 selects the common cause failure evaluation target device type, selects the failure mode and the corresponding system according to the selected device type, and selects the group number of the common cause failure evaluation target device group. Then, the selecting unit 200 receives and selects domestic inherent common cause failure data.

The parameter evaluation unit 300 performs a function of evaluating common cause failure parameters based on the parameter data received through the parameter data unit 100 and the information received through the selection unit 200 1, an input information receiving module 310, a test / maintenance characteristic evaluation module 320, an analysis method evaluation module 330, a fault tree reflection factor evaluation module 340, and an output module 350).

Specifically, the input information receiving module 310 receives the parameter distribution information of the general data source from the parameter data part 100, the common cause failure evaluation target device to be evaluated from the selection part 200, the failure mode, , The number of groups, and the domestic common cause cause failure data information.

The test / maintenance characteristic evaluation module 320 performs evaluation according to the test / maintenance characteristics.

Specifically, the test / maintenance characteristic evaluation module 320 calculates, based on the information received through the input information receiving module 310, a common cause failure parameter for the sequential test or nonsequential test of the common cause failure evaluation target device .

The analysis method evaluation module 330 uses the MGL (Multiple Greek Letter) method applied in the PSA (Probabilistic Safety Assessment) model of domestic nuclear power plants and the appropriate alpha factor method in terms of statistical processing And evaluates the parameters.

The fault tree reflection factor evaluation module 340 evaluates the common cause fault factor applied to the fault tree of the PSA model.

Specifically, the fault tree reflection factor evaluation module 340 evaluates common cause fault factors to be directly applied to the failure rate / fault probability evaluation to be reflected in the fault tree of the PSA model.

The output module 350 outputs the evaluation result.

Hereinafter, a common cause failure parameter evaluation method of the nuclear power plant equipment using the system will be described with reference to FIG.

FIG. 2 is an overall flowchart of a common cause failure parameter evaluation method of a nuclear power plant according to the present invention. As shown in FIG. 2, the selection unit 200 selects a common cause failure evaluation target device type (S10) (S20), and selects the group number of the common cause failure evaluation target device group (S30).

The input information receiving module 310 of the parameter evaluating unit 300 receives the parameter distribution information of the general data source from the parameter data unit 100 and receives the parameter distribution information of the general data source from the selecting unit 200, The test / maintenance characteristic evaluation module 320 of the parameter evaluation unit 300 receives the fault type data of the evaluation target device type, the failure mode, the system, the number of groups and the domestic common cause fault data information in step S40. 310), the common cause failure parameters for the sequential test or the non-sequential test of the device subject to the common cause failure evaluation are evaluated (S50).

Thereafter, the analysis method evaluation module 330 of the parameter evaluating unit 300 uses an MGL (Multiple Greek Letter) method applied in the PSA model of domestic nuclear power plants and an advantageous alpha factor method in terms of statistical processing (S60), and the fault tree reflection factor evaluation module 340 of the parameter evaluation unit 300 evaluates the common cause fault factor to be directly applied to the failure rate / failure probability evaluation to be reflected in the fault tree of the PSA model (S70). Then, the output module 350 of the parameter evaluation unit 300 outputs the evaluation result (S80).

While the present invention has been particularly shown and described with reference to preferred embodiments thereof, it will be understood by those skilled in the art that various changes in form and details may be made therein without departing from the spirit and scope of the invention as defined by the appended claims. It will be appreciated by those skilled in the art that numerous changes and modifications may be made without departing from the invention. Accordingly, all such appropriate modifications and changes, and equivalents thereof, should be regarded as within the scope of the present invention.

S: common cause failure parameter evaluation system of nuclear power plant equipment
100: Parameter data section 200:
300: parameter evaluating unit 310: input information receiving module
320: test / maintenance characteristic evaluation module 330: analysis method evaluation module
340: fault tree reflection factor evaluation module 350: output module

Claims (4)

A parameter data portion storing parameter data;
A selection unit that selects a common cause failure evaluation target device type, selects a failure mode and a corresponding system according to the selected device type, and selects the group number of the common cause failure evaluation target device group;
A parameter evaluating unit for evaluating a common cause failure parameter based on the parameter data received through the parameter data unit and the information received through the input unit; Lt; / RTI >
Wherein the parameter data comprises:
Common cause failure involving operating data of US nuclear power plant Common cause failure evaluated based on general data source and pressurized light water reactor operating data Common source of failure of nuclear power plant equipment characterized by malfunction parameter evaluation system.
delete The method according to claim 1,
Wherein the parameter evaluating unit comprises:
Receiving parameter distribution information of a general data source from the parameter data unit and receiving from the selecting unit a common cause of failure evaluation target device type, a failure mode, a system, a group number, An input information receiving module;
A test / maintenance characteristic evaluation module for evaluating common cause failure parameters for sequential testing or nonsequential testing of common cause failure evaluation devices based on information received through the input information receiving module;
An analysis method evaluation module for evaluating parameters using an MLA (Multiple Greek Letter) method applied in the PSA model of domestic nuclear power plants and a suitable alpha factor method in terms of statistical processing;
A fault tree reflection factor evaluation module for evaluating a common cause fault factor applied to the fault tree of the PSA model; And
An output module outputting an evaluation result; And a failure parameter evaluating system for a common cause failure parameter of the nuclear power plant equipment.
(a) selecting, by the selecting unit, a common cause failure evaluation target device type;
(b) selecting a failure mode and a corresponding system according to the selected device type;
(c) selecting the number of groups of the common cause failure evaluation target device group by the selection unit;
(d) a parameter evaluation unit receiving parameter distribution information of a general data source from the parameter data unit;
(e) receiving a common cause failure evaluation target device type, a failure mode, a system, a group number, and a failure factor data information that are intrinsic common cause cause intrinsic to be evaluated from the parameter evaluation unit selection unit;
(f) evaluating a common cause failure parameter for sequential or nonsequential testing of the common cause failure evaluation device based on the information received through the steps (d) to (e) ;
(g) evaluating parameters using the MGL (Multiple Greek Letter) method and the advantageous alpha factor method in terms of statistical processing applied by the parameter evaluating unit in the PSA model of the domestic nuclear power plant; And
(h) evaluating a common cause failure factor to be directly applied to the failure rate / failure probability evaluation to be reflected in the failure tree of the PSA model, and outputting an evaluation result; Lt; / RTI >
Wherein the parameter data comprises:
Common cause failure involving operating data of US Nuclear Power Plant Common cause failure evaluated based on general data source and pressurized light water reactor operating data Common cause of failure of nuclear plant equipment characterized by failure parameter evaluation method.

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