CN-121997189-A - Risk assessment method, device, equipment and storage medium for high-temperature gas cooled reactor equipment

CN121997189ACN 121997189 ACN121997189 ACN 121997189ACN-121997189-A

Abstract

The invention relates to the technical field of nuclear power generation equipment and discloses a high-temperature gas cooled reactor equipment risk assessment method, device, equipment and storage medium, wherein after acquiring high-temperature gas cooled reactor operation parameters, fault data and associated functional modules are accurately positioned by utilizing a fault assessment model, so that the identification efficiency of the fault data is ensured, and the high-reliability operation requirement of a high-temperature gas cooled reactor is met; finally, the priority and the identification color of different devices are defined by a preset device dividing method, and the pre-built visual data model is combined to help an operator to quickly focus on the critical fault influence device, so that the efficiency of positioning the fault device by the operator is improved, and the efficiency and the accuracy of fault treatment and device risk investigation are improved.

Inventors

YANG FAN
WANG JINXIAO
SUN TIANYU
WANG XIAOJIE
GAO JUNYING
SONG JIAOJIAO

Assignees

华能山东石岛湾核电有限公司

Dates

Publication Date: 20260508
Application Date: 20251224

Claims (10)

1. A method for risk assessment of a high temperature gas cooled reactor apparatus, the method comprising: Based on the collected operation parameters of the high-temperature gas cooled reactor, obtaining fault data and related functional modules thereof by utilizing a trained fault evaluation model, wherein the operation parameters of the high-temperature gas cooled reactor comprise high-temperature gas cooled reactor nuclear measurement data, fan control data, main loop control data, main pressure relief loop data and fuel loading and unloading data; based on the fault data and the associated functional modules, combining a logic flow diagram, and utilizing a multidimensional data screening method to obtain a plurality of fault influencing devices; Based on the plurality of fault influencing devices, a preset device dividing method is utilized to obtain the priority and the corresponding identification color of each fault influencing device; based on the pre-constructed visual data model, marking the data model corresponding to each fault affecting device as a corresponding identification color, and sending the marked visual data model to a display screen.
2. The method of claim 1, wherein the training of the fault assessment model comprises: Based on accident analysis, operation technical specification, probability safety analysis, over-design reference accident evaluation and parameter setting value of equipment of the high-temperature gas cooled reactor, carrying out feature extraction by using a feature extraction model to obtain the safety standard of the high-temperature gas cooled reactor; based on the safety standard of the high-temperature gas cooled reactor, establishing a mapping relation between the operation parameters of the high-temperature gas cooled reactor and the safety standard to obtain a safety standard rule base of the high-temperature gas cooled reactor; Based on historical operation parameters of the high-temperature gas cooled reactor and corresponding functional modules, the high-temperature gas cooled reactor is combined with a safety standard rule base, and the high-temperature gas cooled reactor is trained by utilizing fault tree analysis and a random forest algorithm to obtain a trained fault evaluation model.
3. The method of claim 1, wherein the obtaining a plurality of fault influencing devices based on the fault data and the associated functional modules thereof by using a multidimensional data screening method in combination with a logic flow diagram comprises: deriving by utilizing a logic flow chart based on the functional module associated with the fault data to obtain upstream control equipment and downstream affected equipment; Based on the fault data, calculating the correlation coefficient of the fault data and other equipment operation parameters, and outputting equipment with the phase relation number larger than a preset threshold value as fault related equipment; And integrating the upstream control equipment, the downstream affected equipment and the fault related equipment, and removing repeated equipment to obtain a plurality of fault affected equipment.
4. The method according to claim 1, wherein the obtaining, based on the plurality of fault influencing devices, the priority of each fault influencing device and the corresponding identification color by using a preset device division method includes: The method comprises the steps of obtaining the priority of each fault affecting device by utilizing a priority dividing method in a device dividing method aiming at each fault affecting device, wherein the priority dividing method comprises the steps of dividing the safety limit value, the safety system setting value and the operation limiting condition of the high-temperature gas cooled reactor; Based on the priorities of the plurality of fault affecting devices, the identification color of each fault affecting device is obtained by using an identification color allocation method in a device division method, wherein the identification color allocation method comprises the association relation between the priorities and the corresponding identification colors.
5. The method of claim 1, wherein the constructing of the visual data model comprises: The method comprises the steps of obtaining a three-dimensional model of the whole high-temperature gas cooled reactor by utilizing a method for constructing the three-dimensional model on the basis of a plurality of devices of the high-temperature gas cooled reactor, wherein the three-dimensional model comprises a cabinet model and an internal module model; Based on the operation parameters of a DCS system of the high-temperature gas cooled reactor, respectively establishing a mapping relation between each operation parameter and each module model of the three-dimensional model to obtain an operation parameter-module association database; and matching the received current operation parameters of the DCS system with the corresponding module models based on the mapping relation in the operation parameter-module association database to obtain the visualized data model.
6. The method as recited in claim 1, further comprising: based on the priority of each fault affecting device and the corresponding identification color, sequencing all the fault affecting devices according to the priority to obtain a priority list of the fault affecting devices, and sending the priority list of the fault affecting devices to a display screen.
7. The method as recited in claim 1, further comprising: Responding to the click operation of an external user, and identifying equipment in the area where the click operation of the user is located to obtain target equipment; Screening from a historical database based on the target equipment to obtain data information of the target equipment, wherein the data information comprises defect data records, historical data and maintenance records; And transmitting the data information of the target equipment to a display screen.
8. A risk assessment device for a high-temperature gas cooled reactor apparatus, the device comprising: the fault evaluation module is used for obtaining fault data and related functional modules based on the collected operation parameters of the high-temperature gas cooled reactor by utilizing the trained fault evaluation model, wherein the operation parameters of the high-temperature gas cooled reactor comprise high-temperature gas cooled reactor nuclear measurement data, fan control data, main loop control data, main pressure relief loop data and fuel loading and unloading data; The equipment screening module is used for obtaining a plurality of fault influencing equipment by utilizing a data screening method based on the fault data and the associated functional modules thereof and combining a logic flow chart; the priority classification module is used for obtaining the priority and the corresponding identification color of each fault influence device by using a preset device classification method based on the plurality of fault influence devices; The result display module is used for marking the data model corresponding to each fault affecting device as a corresponding identification color based on the pre-constructed visual data model, and sending the marked visual data model to the display screen.
9. An electronic device, comprising: A memory and a processor, the memory and the processor being communicatively connected to each other, the memory having stored therein computer instructions, the processor executing the computer instructions to perform the high temperature gas cooled reactor apparatus risk assessment method of any one of claims 1 to 7.
10. A computer-readable storage medium having stored thereon computer instructions for causing a computer to perform the high temperature gas cooled reactor apparatus risk assessment method of any one of claims 1 to 7.

Description

Risk assessment method, device, equipment and storage medium for high-temperature gas cooled reactor equipment Technical Field The invention relates to the technical field of nuclear power generation equipment, in particular to a risk assessment method, a risk assessment device, risk assessment equipment and a risk assessment storage medium for high-temperature gas cooled reactor equipment. Background The high temperature gas cooled reactor is a gas cooled reactor technology using helium as a coolant, and can convert nuclear energy into electric energy through a conversion process of nuclear energy-thermal energy-mechanical energy-electric energy. And an operator monitors and controls the equipment of the whole high-temperature gas cooled reactor through equipment parameters of the related equipment of the high-temperature gas cooled reactor provided by the DCS system. In the risk investigation method of the high-temperature gas cooled reactor equipment disclosed in the related technology, after an operator inquires an operation manual of the high-temperature gas cooled reactor manually, the whole high-temperature gas cooled reactor equipment is subjected to investigation in sequence, and the defects of low investigation efficiency and lag fault positioning exist. Disclosure of Invention The invention provides a high-temperature gas cooled reactor equipment risk assessment method, a device, equipment and a storage medium, which are used for solving the problems of low investigation efficiency and lag fault location existing in a high-temperature gas cooled reactor equipment risk investigation method in the related technology. In a first aspect, the invention provides a risk assessment method for high-temperature gas cooled reactor equipment, which comprises the following steps: Based on the collected operation parameters of the high-temperature gas cooled reactor, obtaining fault data and related functional modules thereof by utilizing a trained fault evaluation model, wherein the operation parameters of the high-temperature gas cooled reactor comprise high-temperature gas cooled reactor nuclear measurement data, fan control data, main loop control data, main pressure relief loop data and fuel loading and unloading data; based on the fault data and the associated functional modules, combining a logic flow diagram, and utilizing a multidimensional data screening method to obtain a plurality of fault influencing devices; Based on the plurality of fault influencing devices, a preset device dividing method is utilized to obtain the priority and the corresponding identification color of each fault influencing device; based on the pre-constructed visual data model, marking the data model corresponding to each fault affecting device as a corresponding identification color, and sending the marked visual data model to a display screen. According to the embodiment, after the operation parameters of the high-temperature gas cooled reactor are obtained, the fault evaluation model is utilized to accurately position fault data and related functional modules thereof, the identification efficiency of the fault data is guaranteed, the high-reliability operation requirement of the high-temperature gas cooled reactor is met, then a multi-dimensional data screening method is utilized in combination with a logic flow chart to obtain fault influence equipment related to the fault data, the comprehensive evaluation of the fault influence range is guaranteed, the interference of other irrelevant equipment is reduced, finally the priority and identification colors of different equipment are defined by utilizing a preset equipment dividing method, and an operator is helped to quickly focus on critical fault influence equipment by combining with a pre-built visual data model, so that the positioning efficiency of the fault equipment by the operator is improved, and the efficiency and the accuracy of fault treatment and equipment risk troubleshooting are improved. In an alternative embodiment, the training of the fault assessment model includes: Based on accident analysis, operation technical specification, probability safety analysis, over-design reference accident evaluation and parameter setting value of equipment of the high-temperature gas cooled reactor, carrying out feature extraction by using a feature extraction model to obtain the safety standard of the high-temperature gas cooled reactor; based on the safety standard of the high-temperature gas cooled reactor, establishing a mapping relation between the operation parameters of the high-temperature gas cooled reactor and the safety standard to obtain a safety standard rule base of the high-temperature gas cooled reactor; Based on historical operation parameters of the high-temperature gas cooled reactor and corresponding functional modules, the high-temperature gas cooled reactor is combined with a safety standard rule base, and the fault evaluation model is obtained by trai