技术领域technical field
本发明属于核电站安防领域，更具体地说，本发明涉及一种核电站运行安全指数量化方法和系统。The invention belongs to the field of nuclear power plant security, and more specifically, the invention relates to a method and system for quantifying the operational safety index of a nuclear power plant.
背景技术Background technique
随着国内核电站进入建设、投运、改造高峰期，新设备、新操作员不断投入运营，但是核电站的运行、维修仍然遵循传统依据原始离散数据收集信息和经验判定来解决核电发生的安全问题以及核电设备管理；目前核电设备检测仍然停留在故障诊断状态，核电设备预防性维修依靠运行程序、事故处理程序和运行组织中的值长、运行工程师、安全工程师以及后方的技术中心提供决策支持，该决策体系复杂、智能化程度不高，核安全监控缺乏对核电站正常运行、运行事件及时、有效的诊断和宏观影响有针对性判定。As domestic nuclear power plants enter the peak period of construction, operation, and transformation, new equipment and new operators are continuously put into operation, but the operation and maintenance of nuclear power plants still follow the traditional method of collecting information and empirical judgments based on original discrete data to solve nuclear power safety issues and Nuclear power equipment management: At present, the detection of nuclear power equipment is still in the state of fault diagnosis, and the preventive maintenance of nuclear power equipment relies on operating procedures, accident handling procedures, and decision support provided by the duty chief, operation engineer, safety engineer and the technical center in the operation organization. The decision-making system is complex and the degree of intelligence is not high. Nuclear safety monitoring lacks timely and effective diagnosis and macro-impact judgment on the normal operation of nuclear power plants and operational events.
核电站处于没有报警或者处理报警两个阶段，在没有报警情况下，依靠操作员的知识结合电厂参数对电厂核安全进行判断，认为电厂无需干预。但是，出现报警后，则需要马上处理报警。没有精确分层，仅有最低标准。在参数和电厂的正常运行范围，仅有参数报警值或者预报警值。目前，国内仅有的几个数字化核电站采用数字化仪控设备(DigitalControl System，DCS)，如何使用数字化提升电站安全性，如何对核电安全量化评估，是亟待解决的问题。The nuclear power plant is in two stages of no alarm or alarm processing. In the case of no alarm, the nuclear safety of the plant is judged by relying on the knowledge of the operator and the parameters of the plant, and it is considered that the plant does not need to intervene. However, after an alarm occurs, it is necessary to deal with the alarm immediately. There is no precise stratification, only minimum standards. In the normal operating range of parameters and power plants, there are only parameter alarm values or pre-alarm values. At present, only a few digital nuclear power plants in China use digital instrumentation and control equipment (Digital Control System, DCS). How to use digitalization to improve the safety of power plants and how to quantitatively evaluate nuclear power safety are problems that need to be solved urgently.
发明内容Contents of the invention
本发明的目的在于：提供一种核电站运行安全指数量化方法和系统，在核电站运行过程中，通过破坏值、隐患值、核电设备可靠性能值、人机匹配值、核电站安全边界等级以及事件事故影响值，结合预先设置各个值的加权对核电站安全运行指数进行量化，以实现对核电站运行安全的量化评测，精确了解核电站运行的安全状况。The purpose of the present invention is to: provide a nuclear power plant operation safety index quantification method and system, during the operation of the nuclear power plant, through the damage value, hidden danger value, nuclear power equipment reliability performance value, man-machine matching value, nuclear power plant safety boundary level and event accident impact Combined with the pre-set weighting of each value, the safety operation index of the nuclear power plant is quantified, so as to realize the quantitative evaluation of the operation safety of the nuclear power plant and accurately understand the safety status of the operation of the nuclear power plant.
为了实现上述发明目的，本发明提供了一种核电站运行安全指数量化方法，其包括：In order to achieve the purpose of the above invention, the present invention provides a method for quantifying nuclear power plant operation safety index, which includes:
获取核电站运行参数项的功能数据中的异常功能数据对核电站安全运行的破坏值；Obtain the damage value of the abnormal function data in the functional data of the nuclear power plant operating parameter item to the safe operation of the nuclear power plant;
获取核电站缺陷设备对核电站安全运行的隐患值；Obtain the hidden danger value of defective equipment in nuclear power plants to the safe operation of nuclear power plants;
根据所述破坏值、所述隐患值、核电设备可靠性能值、人机匹配值、核电站安全边界等级以及事件事故影响值，结合预先设置各个值的加权对核电站安全运行指数进行量化。Quantify the nuclear power plant safety operation index according to the damage value, the hidden danger value, the reliability performance value of nuclear power equipment, the human-machine matching value, the safety boundary level of the nuclear power plant, and the impact value of the event accident, combined with the weighting of each value set in advance.
作为本发明核电站运行安全指数量化方法的一种改进，所述方法还包括：采集核电站运行参数项的功能数据，设置运行参数项的重要等级和功能数据的异常度；所述获取核电站运行参数项的功能数据中的异常功能数据对核电站安全运行的破坏值包括，根据异常功能数据对应运行参数项的重要等级和所述异常功能数据的异常度计算所述核电站安全运行的破坏值。As an improvement of the nuclear power plant operation safety index quantification method of the present invention, the method also includes: collecting the functional data of the nuclear power plant operating parameter items, setting the importance level of the operating parameter items and the abnormality of the functional data; the acquisition of the nuclear power plant operating parameter items The damage value of the abnormal function data in the functional data to the safe operation of the nuclear power plant includes calculating the damage value of the safe operation of the nuclear power plant according to the importance level of the operation parameter item corresponding to the abnormal function data and the abnormality degree of the abnormal function data.
作为本发明核电站运行安全指数量化方法的一种改进，所述方法还包括：As an improvement of the nuclear power plant operation safety index quantification method of the present invention, the method also includes:
设置核电站设备的缺陷等级和相应缺陷等级的修复时间，所述获取核电站缺陷设备对核电站安全运行的隐患值包括，根据所述核电站缺陷设备的缺陷等级和在核电站运行中的作用计算得到隐患值。The defect level of the nuclear power plant equipment and the repair time of the corresponding defect level are set, and the acquisition of the hidden danger value of the nuclear power plant defective equipment to the safe operation of the nuclear power plant includes calculating the hidden danger value according to the defect level of the nuclear power plant defective equipment and its role in the operation of the nuclear power plant.
作为本发明核电站运行安全指数量化方法的一种改进，所述方法还包括：As an improvement of the nuclear power plant operation safety index quantification method of the present invention, the method also includes:
建立核电站设备异常和故障分析模型，根据所述异常和故障分析模型和所述核电站设备的性能参数得到所述核电设备可靠性能值。A nuclear power plant equipment abnormality and failure analysis model is established, and the nuclear power equipment reliability performance value is obtained according to the abnormality and failure analysis model and the performance parameters of the nuclear power plant equipment.
作为本发明核电站运行安全指数量化方法的一种改进，所述方法还包括：As an improvement of the nuclear power plant operation safety index quantification method of the present invention, the method also includes:
根据采集的人机不匹配错误建立人机匹配性分析模型，根据所述人机匹配性分析模型和任务执行评价值得到所述人机匹配值。A man-machine matching analysis model is established according to the collected man-machine mismatch errors, and the man-machine matching value is obtained according to the man-machine matching analysis model and task execution evaluation values.
作为本发明核电站运行安全指数量化方法的一种改进，所述核电站安全边界等级包括：As an improvement of the nuclear power plant operation safety index quantification method of the present invention, the safety boundary level of the nuclear power plant includes:
核电站正常运行安全边界级、核电站事件运行安全边界级，以及核电站事故运行安全边界级。The safety boundary level of normal operation of nuclear power plants, the safety boundary level of nuclear power plant event operation, and the safety boundary level of nuclear power plant accident operation.
作为本发明核电站运行安全指数量化方法的一种改进，所述方法还包括：As an improvement of the nuclear power plant operation safety index quantification method of the present invention, the method also includes:
根据所述核电站安全运行指数的量化值，判断所述核电站运行是否安全。According to the quantitative value of the safe operation index of the nuclear power plant, it is judged whether the operation of the nuclear power plant is safe.
为了实现上述发明目的，本发明还提供了一种核电站运行安全指数量化系统，其包括：In order to achieve the purpose of the above invention, the present invention also provides a nuclear power plant operation safety index quantification system, which includes:
第一获取模块，用于获取核电站运行参数项的功能数据中的异常功能数据对核电站安全运行的破坏值；The first acquisition module is used to acquire the damage value of the abnormal function data in the functional data of the nuclear power plant operation parameter item to the safe operation of the nuclear power plant;
第二获取模块，用于获取核电站缺陷设备对核电站安全运行的隐患值；The second acquisition module is used to acquire the hidden danger value of the defective equipment of the nuclear power plant to the safe operation of the nuclear power plant;
量化模块，根据所述破坏值、所述隐患值、核电设备可靠性能值、人机匹配值、核电站安全边界等级以及事件事故影响值，结合预先设置各个值的加权对核电站安全运行指数进行量化。The quantification module quantifies the safety operation index of the nuclear power plant according to the damage value, the hidden danger value, the reliability performance value of nuclear power equipment, the man-machine matching value, the safety boundary level of the nuclear power plant, and the impact value of the accident, combined with the weighting of each value set in advance.
作为本发明核电站运行安全指数量化系统的一种改进，所述第一获取模块包括：As an improvement of the nuclear power plant operation safety index quantification system of the present invention, the first acquisition module includes:
采集单元，用于采集核电站运行参数项的功能数据；The collection unit is used to collect the functional data of the operating parameter items of the nuclear power plant;
设置单元，用于设置运行参数项的重要等级和功能数据的异常度；The setting unit is used to set the importance level of the operation parameter items and the abnormality degree of the functional data;
计算单元，用于根据异常功能数据对应运行参数项的重要等级和所述异常功能数据的异常度计算所述核电站安全运行的破坏值。The calculation unit is used to calculate the damage value of the safe operation of the nuclear power plant according to the importance level of the operation parameter item corresponding to the abnormal function data and the abnormality degree of the abnormal function data.
作为本发明核电站运行安全指数量化系统的一种改进，所述系统还包括：As an improvement of the nuclear power plant operation safety index quantification system of the present invention, the system also includes:
设计模块，用于设置核电站设备的缺陷等级和相应缺陷等级的修复时间，所述第二获取模块还用于，根据所述设计模块设置的核电站缺陷设备的缺陷等级和在核电站运行中的作用计算得到隐患值。The design module is used to set the defect level of the nuclear power plant equipment and the repair time of the corresponding defect level, and the second acquisition module is also used to calculate the defect level of the nuclear power plant defect equipment set by the design module and its function in the operation of the nuclear power plant Get hidden value.
作为本发明核电站运行安全指数量化系统的一种改进，所述系统还包括：As an improvement of the nuclear power plant operation safety index quantification system of the present invention, the system also includes:
建模模块，用于建立核电站设备异常和故障分析模型；Modeling module, used to establish abnormal and fault analysis models of nuclear power plant equipment;
可靠性能值测评模块，用于根据所述异常和故障分析模型和所述核电站设备的性能参数得到所述核电设备可靠性能值。The reliability performance value evaluation module is used to obtain the reliability performance value of the nuclear power equipment according to the abnormality and failure analysis model and the performance parameters of the nuclear power plant equipment.
作为本发明核电站运行安全指数量化系统的一种改进，所述系统还包括：As an improvement of the nuclear power plant operation safety index quantification system of the present invention, the system also includes:
人机匹配性模块，用于根据采集的人机不匹配错误建立人机匹配性分析模型；The man-machine matching module is used to establish a man-machine matching analysis model according to the collected man-machine mismatch errors;
人机匹配值测评模块，用于根据所述人机匹配性分析模型和任务执行评价值得到所述人机匹配值。The man-machine matching value evaluation module is used to obtain the man-machine matching value according to the man-machine matching analysis model and task execution evaluation value.
作为本发明核电站运行安全指数量化系统的一种改进，所述系统还包括：As an improvement of the nuclear power plant operation safety index quantification system of the present invention, the system also includes:
判断模块，用于根据所述核电站安全运行指数的量化值，判断所述核电站运行是否安全。A judging module, configured to judge whether the nuclear power plant is safe to operate according to the quantified value of the nuclear power plant safety operation index.
与现有技术相比，本发明核电站运行安全指数量化方法和系统具有以下有益技术效果：获取核电站运行参数项的功能数据中的异常功能数据对核电站安全运行的破坏值和核电站缺陷设备对核电站安全运行的隐患值；根据获得的破坏值、隐患值、核电设备可靠性能值、人机匹配值、核电站安全边界等级以及事件事故影响值，结合预先设置各个值的加权对核电站安全运行指数进行量化，解决了核电站安全运行数据离散、无法精确评估核电站安全等级的问题。此外，由于采集了核电站运行中安全方面的绝大部分数据，通过建立的模型进行评测，实现了核电站全面的安全测评、数字化测评，取得很好的技术效果。Compared with the prior art, the nuclear power plant operation safety index quantification method and system of the present invention have the following beneficial technical effects: the damage value of the abnormal function data in the functional data of the nuclear power plant operating parameter items to the safe operation of the nuclear power plant and the impact of nuclear power plant defect equipment on the safety of the nuclear power plant are obtained. Hidden danger value of operation; according to the obtained damage value, hidden danger value, nuclear power equipment reliability performance value, man-machine matching value, nuclear power plant safety boundary level and event accident impact value, combined with the pre-set weighting of each value to quantify the nuclear power plant safety operation index, It solves the problem that the safety operation data of the nuclear power plant is discrete and cannot accurately evaluate the safety level of the nuclear power plant. In addition, due to the collection of most of the safety data in the operation of nuclear power plants and the evaluation through the established model, the comprehensive safety evaluation and digital evaluation of nuclear power plants have been realized, and good technical results have been achieved.
附图说明Description of drawings
下面结合附图和具体实施方式，对本发明核电站运行安全指数量化方法和系统进行详细说明，其中：The method and system for quantifying the nuclear power plant operation safety index of the present invention will be described in detail below in conjunction with the accompanying drawings and specific implementation methods, wherein:
图1提供了本发明核电站运行安全指数量化方法的一个实施例的流程图。Fig. 1 provides a flow chart of an embodiment of the method for quantifying the operational safety index of a nuclear power plant according to the present invention.
图2提供了本发明核电站运行安全指数量化方法的又一个实施例的流程图。Fig. 2 provides a flow chart of another embodiment of the method for quantifying the operational safety index of a nuclear power plant according to the present invention.
图3提供了本发明核电站运行安全指数量化系统的一个实施例的示意图。Fig. 3 provides a schematic diagram of an embodiment of the nuclear power plant operation safety index quantification system of the present invention.
图4提供了本发明核电站运行安全指数量化系统的又一个实施例的示意图。Fig. 4 provides a schematic diagram of another embodiment of the nuclear power plant operation safety index quantification system of the present invention.
图5提供了本发明核电站运行安全指数量化系统的又一个实施例的示意图。Fig. 5 provides a schematic diagram of another embodiment of the nuclear power plant operation safety index quantification system of the present invention.
具体实施方式detailed description
为了使本发明的发明目的、技术方案及其技术效果更加清晰，以下结合附图和具体实施方式，对本发明进行进一步详细说明。应当理解的是，本说明书中描述的具体实施方式仅仅是为了解释本发明，并非为了限定本发明。In order to make the purpose, technical solution and technical effect of the present invention clearer, the present invention will be further described in detail below in conjunction with the accompanying drawings and specific embodiments. It should be understood that the specific implementations described in this specification are only for explaining the present invention, not for limiting the present invention.
请结合参看图1，图1提供了一种核电站运行安全指数量化方法，其包括：Please refer to Figure 1 in conjunction with Figure 1. Figure 1 provides a quantitative method for nuclear power plant operation safety index, which includes:
步骤101，获取核电站运行参数项的功能数据中的异常功能数据对核电站安全运行的破坏值。Step 101, acquiring the damage value of the abnormal function data in the functional data of the nuclear power plant operating parameter item to the safe operation of the nuclear power plant.
具体的，采集核电站运行参数项的功能数据，设置运行参数项的重要等级和功能数据的异常度；获取核电站运行参数项的功能数据中的异常功能数据对核电站安全运行的破坏值包括，根据异常功能数据对应运行参数项的重要等级和异常功能数据的异常度计算核电站安全运行的破坏值。Specifically, collect the functional data of the nuclear power plant operating parameter items, set the importance level of the operating parameter items and the abnormality of the functional data; obtain the damage value of the abnormal functional data in the functional data of the nuclear power plant operating parameter items to the safe operation of the nuclear power plant, including, according to the abnormality The function data corresponds to the importance level of the operation parameter items and the abnormality degree of the abnormal function data to calculate the damage value of the safe operation of the nuclear power plant.
一般的，为充分了解核电站运行当前的状况，可建立数据库，收集核电站运行全部功能数据，将系统自动产生的数据和人为干预数据、人为维护数据全部收集整理，同时针对不同刷新速率全部收集，要求形成全部功能数据集合。Generally, in order to fully understand the current status of nuclear power plant operation, a database can be established to collect all functional data of nuclear power plant operation, collect and sort out the data automatically generated by the system, human intervention data, and human maintenance data, and at the same time collect all data for different refresh rates. Form all functional data sets.
设置核电站正常运行数据的标准值或标准范围，对所有运行数据中偏离设置的标准值或超过设置的标准范围的数据进行识别，认定为异常数据。或者，设置运行参数项功能数据的异常度，对功能数据符合设置的异常度，即可认定为异常数据。可选的，对功能数据进行重要性分级，即各功能数据有不同的重要等级。根据异常功能数据对应运行参数项的重要等级和异常功能数据的异常度计算核电站安全运行的破坏值，该破坏值即异常功能数据对核电站运行的影响值。Set the standard value or standard range of the normal operating data of the nuclear power plant, and identify all operating data that deviate from the set standard value or exceed the set standard range, and identify them as abnormal data. Alternatively, set the abnormality degree of the functional data of the operation parameter item, and if the functional data meets the set abnormality degree, it can be identified as abnormal data. Optionally, importance classification is performed on the functional data, that is, each functional data has different importance levels. The damage value of the safe operation of the nuclear power plant is calculated according to the importance level of the operation parameter items corresponding to the abnormal function data and the abnormal degree of the abnormal function data, and the damage value is the influence value of the abnormal function data on the operation of the nuclear power plant.
步骤103，获取核电站缺陷设备对核电站安全运行的隐患值；Step 103, obtaining the hidden danger value of the defective equipment of the nuclear power plant to the safe operation of the nuclear power plant;
具体的，设置核电站设备的缺陷等级和相应缺陷等级的修复时间，获取核电站缺陷设备对核电站安全运行的隐患值包括，根据核电站缺陷设备的缺陷等级和在核电站运行中的作用计算得到隐患值。Specifically, setting the defect level of nuclear power plant equipment and the repair time of the corresponding defect level, and obtaining the hidden danger value of the nuclear power plant defective equipment to the safe operation of the nuclear power plant includes calculating the hidden danger value according to the defect level of the nuclear power plant defective equipment and its role in the operation of the nuclear power plant.
一般的，对核电站固有不完善和因为运行实验、维修、设备更换等引入的缺陷进行分类，设置核电站设备的缺陷等级，结合其在不同核电站运行工况所起不同作用和缺陷等级相应的修复时间，计算得到核电站设备对核电站运行的隐患值，即核电站设备缺陷对核电站运行安全的影响值。In general, classify the inherent imperfections of nuclear power plants and the defects introduced by operating experiments, maintenance, equipment replacement, etc., set the defect levels of nuclear power plant equipment, and combine their different roles in different operating conditions of nuclear power plants and the repair time corresponding to defect levels , the hidden danger value of nuclear power plant equipment to nuclear power plant operation is calculated, that is, the impact value of nuclear power plant equipment defects on nuclear power plant operation safety.
步骤105，根据破坏值、隐患值、核电设备可靠性能值、人机匹配值、核电站安全边界等级以及事件事故影响值，结合预先设置各个值的加权对核电站安全运行指数进行量化。Step 105, quantify the nuclear power plant safety operation index according to the damage value, hidden danger value, nuclear power equipment reliability performance value, man-machine matching value, nuclear power plant safety boundary level and event accident impact value, combined with the weighting of each value set in advance.
通过前述方式得到所需的破坏值和隐患值。为量化核电站安全运行指数，需要得到核电设备可靠性能值、人机匹配值、核电站安全边界等级以及事件事故影响值。Obtain the required damage value and hidden danger value through the aforementioned method. In order to quantify the safe operation index of nuclear power plants, it is necessary to obtain the reliability performance value of nuclear power equipment, man-machine matching value, safety boundary level of nuclear power plant and accident impact value.
具体的，建立核电站设备异常和故障分析模型，根据异常和故障分析模型和核电站设备的性能参数得到核电设备可靠性能值。对核电站设备异常和故障进行模型建立，根据核电站设备固有设计参数进行，以当前核电站运行状态和当前执行任务为基准，对核电站设备的重要性和敏感性进行分析，确定重要设备监测的规则，确定核电站设备可靠性能值。Specifically, a nuclear power plant equipment abnormality and failure analysis model is established, and the reliability performance value of the nuclear power equipment is obtained according to the abnormality and failure analysis model and the performance parameters of the nuclear power plant equipment. Modeling of nuclear power plant equipment abnormalities and failures is carried out according to the inherent design parameters of nuclear power plant equipment, based on the current nuclear power plant operating status and current execution tasks, the importance and sensitivity of nuclear power plant equipment are analyzed, and the rules for important equipment monitoring are determined. Reliability performance value of nuclear power plant equipment.
根据采集的人机不匹配错误建立人机匹配性分析模型，根据人机匹配性分析模型和任务执行评价值得到人机匹配值。对人机不匹配错误进行收集和统计，对人操作可靠性与有效性建立模型，以人是否能够完成其针对人机界面上的任务客观评价，确定人机匹配值。The man-machine matching analysis model is established according to the collected man-machine mismatch errors, and the man-machine matching value is obtained according to the man-machine matching analysis model and the evaluation value of task execution. Collect and collect statistics on human-machine mismatch errors, establish a model for the reliability and effectiveness of human operation, and determine the human-machine matching value based on the objective evaluation of whether the human can complete the tasks on the human-machine interface.
核电站安全边界等级分为：核电站正常运行安全边界级、核电站事件运行安全边界级，以及核电站事故运行安全边界级。The safety boundary level of nuclear power plants is divided into: the safety boundary level of normal operation of nuclear power plants, the safety boundary level of nuclear power plant event operation, and the safety boundary level of nuclear power plant accident operation.
根据破坏值、隐患值、核电设备可靠性能值、人机匹配值、核电站安全边界等级以及事件事故影响值，结合预先设置各个值的加权对核电站安全运行指数进行量化，并得到核电站安全运行量化值。According to the damage value, hidden danger value, nuclear power equipment reliability performance value, man-machine matching value, nuclear power plant safety boundary level and event accident impact value, combined with the weighting of each preset value, the nuclear power plant safety operation index is quantified, and the nuclear power plant safety operation quantitative value is obtained .
可选的，根据核电站安全运行指数的量化值，判断核电站运行是否安全。具体包括，根据预先设置的核电站安全运行指数标准，根据量化值判断核电站运行安全等级。Optionally, it is judged whether the operation of the nuclear power plant is safe or not according to the quantified value of the safe operation index of the nuclear power plant. Specifically, it includes judging the operation safety level of the nuclear power plant based on the quantitative value according to the preset safety operation index standard of the nuclear power plant.
本发明实施方式通过获取核电站运行参数项的功能数据中的异常功能数据对核电站安全运行的破坏值和核电站缺陷设备对核电站安全运行的隐患值；根据获得的破坏值、隐患值、核电设备可靠性能值、人机匹配值、核电站安全边界等级以及事件事故影响值，结合预先设置各个值的加权对核电站安全运行指数进行量化，解决了核电站安全运行数据离散、无法精确评估核电站安全等级的问题。此外，由于采集了核电站运行中安全方面的绝大部分数据，通过建立的模型进行评测，实现了核电站全面的安全测评、数字化测评。The implementation mode of the present invention obtains the damage value of the abnormal function data in the functional data of the nuclear power plant operation parameter item to the safe operation of the nuclear power plant and the hidden danger value of the nuclear power plant defect equipment to the safe operation of the nuclear power plant; according to the obtained damage value, hidden danger value, nuclear power equipment reliability performance Value, man-machine matching value, nuclear power plant safety boundary level, and accident impact value, combined with the weighting of each value preset to quantify the nuclear power plant safety operation index, solves the problem of discrete nuclear power plant safety operation data and the inability to accurately evaluate the safety level of nuclear power plants. In addition, due to the collection of most of the safety data in the operation of nuclear power plants, the evaluation is carried out through the established model, and the comprehensive safety evaluation and digital evaluation of nuclear power plants are realized.
请结合参看图2，图2提供了一种核电站运行安全指数量化系统的一个实施例，根据核电站缺陷设备的缺陷等级和在核电站运行中的作用计算得到隐患值，包括：通过对核电站固有不完善和因为运行实验、维修、设备更换等引入的缺陷进行分类，收集核电站设备计划维修信息、系统试验信息、系统实施遗留项、非预期人员介入信息以及功能临时变更信息，通过预先设定的缺陷分析路径，对核电站设备进行缺陷等级分类，结合其在不同核电站运行工况所起不同作用和缺陷等级相应的修复时间，计算得到核电站设备对核电站运行的隐患值，即核电站设备缺陷对核电站运行安全的影响值。Please refer to Figure 2. Figure 2 provides an embodiment of a nuclear power plant operation safety index quantification system. The hidden danger value is calculated according to the defect level of nuclear power plant defect equipment and its role in the operation of the nuclear power plant, including: through the inherent imperfection of the nuclear power plant Classify and classify defects introduced due to operation experiments, maintenance, equipment replacement, etc., collect planned maintenance information of nuclear power plant equipment, system test information, system implementation legacy items, unexpected personnel intervention information and temporary function change information, and analyze through preset defects Path, classify the defect levels of nuclear power plant equipment, combine the different roles it plays in different nuclear power plant operating conditions and the repair time corresponding to the defect level, calculate the hidden danger value of nuclear power plant equipment to the operation of nuclear power plants, that is, the impact of nuclear power plant equipment defects on nuclear power plant operation safety influence value.
请结合参看图3，图3提供了一种核电站运行安全指数量化系统的一个实施例，其包括：第一获取模块301、第二获取模块303以及量化模块305，其中：Please refer to FIG. 3 in conjunction with FIG. 3. FIG. 3 provides an embodiment of a nuclear power plant operation safety index quantification system, which includes: a first acquisition module 301, a second acquisition module 303, and a quantification module 305, wherein:
第一获取模块301，用于获取核电站运行参数项的功能数据中的异常功能数据对核电站安全运行的破坏值；The first acquisition module 301 is used to acquire the damage value of the abnormal function data in the functional data of the nuclear power plant operating parameter item to the safe operation of the nuclear power plant;
第二获取模块303，用于获取核电站缺陷设备对核电站安全运行的隐患值；The second acquisition module 303 is used to acquire the hidden danger value of the defective equipment of the nuclear power plant to the safe operation of the nuclear power plant;
量化模块305，根据第一获取模块301获得的破坏值、第二获取模块303获得的隐患值、核电设备可靠性能值、人机匹配值、核电站安全边界等级以及事件事故影响值，结合预先设置各个值的加权对核电站安全运行指数进行量化。The quantification module 305, according to the damage value obtained by the first acquisition module 301, the hidden danger value obtained by the second acquisition module 303, the reliability performance value of the nuclear power equipment, the man-machine matching value, the safety boundary level of the nuclear power plant and the accident impact value, combined with the pre-set various The weighting of the value quantifies the safe operation index of the nuclear power plant.
请结合参看图4，图4提供了一种核电站运行安全指数量化系统的一个实施例，其包括：第一获取模块401、设计模块403、第二获取模块405、建模模块407、可靠性能值测评模块409、人机匹配性模块411、人机匹配值测评模块413、量化模块415以及判断模块417，其中，第一获取模块401包括采集单元4011、设置单元4013以及计算单元4015，具体的：Please refer to Fig. 4, Fig. 4 provides an embodiment of a nuclear power plant operation safety index quantification system, which includes: a first acquisition module 401, a design module 403, a second acquisition module 405, a modeling module 407, a reliability performance value Evaluation module 409, man-machine matching module 411, man-machine matching value evaluation module 413, quantification module 415 and judgment module 417, wherein the first acquisition module 401 includes an acquisition unit 4011, a setting unit 4013 and a calculation unit 4015, specifically:
第一获取模块401，用于获取核电站运行参数项的功能数据中的异常功能数据对核电站安全运行的破坏值，其中，采集单元4011，用于采集核电站运行参数项的功能数据；The first acquisition module 401 is used to acquire the damage value of the abnormal function data in the functional data of the nuclear power plant operating parameter items to the safe operation of the nuclear power plant, wherein the acquisition unit 4011 is used to acquire the functional data of the nuclear power plant operating parameter items;
一般的，为充分了解核电站运行当前的状况，采集单元4011可建立数据库，收集核电站运行全部功能数据，将系统自动产生的数据和人为干预数据、人为维护数据全部收集整理，同时针对不同刷新速率全部收集，要求形成全部功能数据集合。Generally, in order to fully understand the current status of the nuclear power plant operation, the acquisition unit 4011 can establish a database to collect all functional data of the nuclear power plant operation, collect and organize the data automatically generated by the system, human intervention data, and human maintenance data. Collection requires the formation of all functional data sets.
设置核电站正常运行数据的标准值或标准范围，对所有运行数据中偏离设置的标准值或超过设置的标准范围的数据进行识别，认定为异常数据。或者，设置运行参数项功能数据的异常度，对功能数据符合设置的异常度，即可认定为异常数据。可选的，对功能数据进行重要性分级，即各功能数据有不同的重要等级。根据异常功能数据对应运行参数项的重要等级和异常功能数据的异常度计算核电站安全运行的破坏值，该破坏值即异常功能数据对核电站运行的影响值。Set the standard value or standard range of the normal operating data of the nuclear power plant, and identify all operating data that deviate from the set standard value or exceed the set standard range, and identify them as abnormal data. Alternatively, set the abnormality degree of the functional data of the operation parameter item, and if the functional data meets the set abnormality degree, it can be identified as abnormal data. Optionally, importance classification is performed on the functional data, that is, each functional data has different importance levels. The damage value of the safe operation of the nuclear power plant is calculated according to the importance level of the operation parameter items corresponding to the abnormal function data and the abnormal degree of the abnormal function data, and the damage value is the influence value of the abnormal function data on the operation of the nuclear power plant.
设置单元4013，用于设置运行参数项的重要等级和功能数据的异常度；The setting unit 4013 is used to set the importance level of the operation parameter items and the abnormality degree of the functional data;
计算单元4015，用于根据异常功能数据对应运行参数项的重要等级和异常功能数据的异常度计算核电站安全运行的破坏值。The calculation unit 4015 is used to calculate the damage value of the safe operation of the nuclear power plant according to the importance level of the operation parameter items corresponding to the abnormal function data and the abnormality degree of the abnormal function data.
设计模块403，用于设置核电站设备的缺陷等级和相应缺陷等级的修复时间；The design module 403 is used to set the defect level of the nuclear power plant equipment and the repair time of the corresponding defect level;
第二获取模块405，根据设计模块408设置的核电站缺陷设备的缺陷等级和在核电站运行中的作用计算得到隐患值。The second acquisition module 405 calculates the hidden danger value according to the defect level of the defective equipment of the nuclear power plant set by the design module 408 and its function in the operation of the nuclear power plant.
建模模块407，用于建立核电站设备异常和故障分析模型；The modeling module 407 is used to establish a nuclear power plant equipment abnormality and failure analysis model;
一般的，建模模块407对核电站固有不完善和因为运行实验、维修、设备更换等引入的缺陷进行分类，建模模块407设置核电站设备的缺陷等级。Generally, the modeling module 407 classifies the inherent imperfections of the nuclear power plant and the defects introduced by running experiments, maintenance, equipment replacement, etc., and the modeling module 407 sets the defect level of the nuclear power plant equipment.
可靠性能值测评模块409，用于根据建模模块407建立的异常和故障分析模型和核电站设备的性能参数得到核电设备可靠性能值。The reliability performance evaluation module 409 is used to obtain the reliability performance value of the nuclear power equipment according to the abnormality and failure analysis model established by the modeling module 407 and the performance parameters of the nuclear power plant equipment.
可靠性能值测评模块409结合其在不同核电站运行工况所起不同作用和缺陷等级相应的修复时间，计算得到核电站设备对核电站运行的隐患值，即核电站设备缺陷对核电站运行安全的影响值。The reliability performance evaluation module 409 calculates the hidden danger value of the nuclear power plant equipment to the operation of the nuclear power plant, that is, the impact value of the nuclear power plant equipment defect on the operation safety of the nuclear power plant, by combining its different roles in different nuclear power plant operating conditions and the repair time corresponding to the defect level.
人机匹配性模块411，用于根据采集的人机不匹配错误建立人机匹配性分析模型；The man-machine matching module 411 is used to establish a man-machine matching analysis model according to the collected man-machine mismatch errors;
人机匹配值测评模块413，用于根据人机匹配性模块411采集的人机匹配性分析模型和任务执行评价值得到所述人机匹配值。The man-machine matching value evaluation module 413 is used to obtain the man-machine matching value according to the man-machine matching analysis model collected by the man-machine matching module 411 and the evaluation value of task execution.
量化模块415，用于根据计算单元4015计算得到破坏值、第二获取模块405获得的隐患值、可靠性能值测评模块409获得的核电设备可靠性能值、人机匹配值测评模块413获得的人机匹配值、核电站安全边界等级以及事件事故影响值，结合预先设置各个值的加权对核电站安全运行指数进行量化。The quantification module 415 is used to obtain the damage value calculated by the calculation unit 4015, the hidden danger value obtained by the second acquisition module 405, the reliability performance value of nuclear power equipment obtained by the reliability performance value evaluation module 409, and the human-machine matching value evaluation module 413. The matching value, the safety boundary level of the nuclear power plant and the impact value of the event accident are combined with the pre-set weighting of each value to quantify the safe operation index of the nuclear power plant.
核电站安全边界等级分为：核电站正常运行安全边界级、核电站事件运行安全边界级，以及核电站事故运行安全边界级。The safety boundary level of nuclear power plants is divided into: the safety boundary level of normal operation of nuclear power plants, the safety boundary level of nuclear power plant event operation, and the safety boundary level of nuclear power plant accident operation.
判断模块417，用于根据量化模块415获得的核电站安全运行指数的量化值，判断核电站运行是否安全。The judging module 417 is configured to judge whether the operation of the nuclear power plant is safe according to the quantified value of the nuclear power plant safety operation index obtained by the quantifying module 415 .
可选的，判断模块417根据核电站安全运行指数的量化值，判断核电站运行是否安全，具体包括，判断模块417根据预先设置的核电站安全运行指数标准，根据量化值判断核电站运行安全等级。Optionally, the judging module 417 judges whether the operation of the nuclear power plant is safe according to the quantified value of the safe operation index of the nuclear power plant. Specifically, the judging module 417 judges the operation safety level of the nuclear power plant according to the quantified value according to the preset safe operation index standard of the nuclear power plant.
本发明实施方式通过获取核电站运行参数项的功能数据中的异常功能数据对核电站安全运行的破坏值和核电站缺陷设备对核电站安全运行的隐患值；根据获得的破坏值、隐患值、核电设备可靠性能值、人机匹配值、核电站安全边界等级以及事件事故影响值，结合预先设置各个值的加权对核电站安全运行指数进行量化，解决了核电站安全运行数据离散、无法精确评估核电站安全等级的问题。此外，由于采集了核电站运行中安全方面的绝大部分数据，通过建立的模型进行评测，实现了核电站全面的安全测评、数字化测评，取得很好的技术效果。The implementation mode of the present invention obtains the damage value of the abnormal function data in the functional data of the nuclear power plant operation parameter item to the safe operation of the nuclear power plant and the hidden danger value of the nuclear power plant defect equipment to the safe operation of the nuclear power plant; according to the obtained damage value, hidden danger value, nuclear power equipment reliability performance Value, man-machine matching value, nuclear power plant safety boundary level, and accident impact value, combined with the weighting of each value preset to quantify the nuclear power plant safety operation index, solves the problem of discrete nuclear power plant safety operation data and the inability to accurately evaluate the safety level of nuclear power plants. In addition, due to the collection of most of the safety data in the operation of nuclear power plants and the evaluation through the established model, the comprehensive safety evaluation and digital evaluation of nuclear power plants have been realized, and good technical results have been achieved.
请结合参看图5，图5提供了一种核电站运行安全指数量化系统的示意图，第一获取模块获取核电站运行参数项的功能数据第一获取模块，用于以一预设时间周期向每个功能服务器发送相应的生命信号；功能数据收集模块收集人和系统相关数据，同时收集上游设计数据和核电站功能组态数据，收集核电站最全数据。收集的数据主要包括：人员失误数据、人员干预统计数据、工艺参数、设备参数、核电站管理数据以及核电站上游输入数据等。当然，第一获取模块获得的数据不仅仅限于上述数据。Please refer to Fig. 5. Fig. 5 provides a schematic diagram of a nuclear power plant operation safety index quantification system. The first acquisition module acquires the functional data of the nuclear power plant operating parameter items. The server sends corresponding life signals; the functional data collection module collects data related to people and systems, and at the same time collects upstream design data and functional configuration data of nuclear power plants to collect the most complete data of nuclear power plants. The collected data mainly include: personnel error data, personnel intervention statistics, process parameters, equipment parameters, nuclear power plant management data, and upstream input data of nuclear power plants. Of course, the data obtained by the first obtaining module is not limited to the above data.
系统的实施方法和流程可以参见前述实施例中介绍的方法实施例，此处不再赘述。For the implementation method and process of the system, reference may be made to the method embodiments introduced in the foregoing embodiments, and details are not repeated here.
结合以上对本发明的详细描述可以看出，相对于现有技术，本发明至少具有以下有益技术效果：通过获取核电站运行参数项的功能数据中的异常功能数据对核电站安全运行的破坏值和核电站缺陷设备对核电站安全运行的隐患值；根据获得的破坏值、隐患值、核电设备可靠性能值、人机匹配值、核电站安全边界等级以及事件事故影响值，结合预先设置各个值的加权对核电站安全运行指数进行量化，解决了核电站安全运行数据离散、无法精确评估核电站安全等级的问题。此外，由于采集了核电站运行中安全方面的绝大部分数据，通过建立的模型进行评测，实现了核电站全面的安全测评、数字化测评。另外，安全量化过程中，将人为的失误操作以及管理因素都纳入安全评测和量化过程，安全评测结果和量化结果更准确，取得很好的技术效果。In conjunction with the above detailed description of the present invention, it can be seen that, compared with the prior art, the present invention has at least the following beneficial technical effects: the damage value of the safe operation of the nuclear power plant and the defects of the nuclear power plant by obtaining the abnormal function data in the functional data of the nuclear power plant operating parameters The hidden danger value of the equipment to the safe operation of the nuclear power plant; according to the obtained damage value, hidden danger value, nuclear power equipment reliability performance value, man-machine matching value, nuclear power plant safety boundary level and event accident impact value, combined with the weighting of each pre-set value to evaluate the safe operation of the nuclear power plant The quantification of the index solves the problem of discrete nuclear power plant safety operation data and the inability to accurately evaluate the safety level of nuclear power plants. In addition, due to the collection of most of the safety data in the operation of nuclear power plants, the evaluation is carried out through the established model, and the comprehensive safety evaluation and digital evaluation of nuclear power plants are realized. In addition, in the process of safety quantification, human error operation and management factors are included in the safety evaluation and quantification process, the safety evaluation results and quantification results are more accurate, and good technical effects are achieved.
根据上述原理，本发明还可以对上述实施方式进行适当的变更和修改。因此，本发明并不局限于上面揭示和描述的具体实施方式，对本发明的一些修改和变更也应当落入本发明的权利要求的保护范围内。此外，尽管本说明书中使用了一些特定的术语，但这些术语只是为了方便说明，并不对本发明构成任何限制。According to the above principles, the present invention can also make appropriate changes and modifications to the above embodiments. Therefore, the present invention is not limited to the specific embodiments disclosed and described above, and some modifications and changes to the present invention should also fall within the protection scope of the claims of the present invention. In addition, although some specific terms are used in this specification, these terms are only for convenience of description and do not constitute any limitation to the present invention.
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| CB03 | Change of inventor or designer information | ||
| CB03 | Change of inventor or designer information | Inventor after:Tan Ke Inventor after:Liu Yanzi Inventor after:Liu Zhen Inventor after:Peng Huaqing Inventor after:Tian Yong Inventor after:Gao Feng Inventor after:Chen Weihua Inventor after:Sun Yongbin Inventor after:Sun Qi Inventor after:Xie Hongyun Inventor after:Wang Ting Inventor after:Lu Chao Inventor after:Gu Haixia Inventor before:Tan Ke Inventor before:Liu Yanzi Inventor before:Liu Zhen Inventor before:Peng Huaqing Inventor before:Tian Yong Inventor before:Sun Yongbin Inventor before:Chen Weihua Inventor before:Gao Feng Inventor before:Sun Qi Inventor before:Xie Hongyun Inventor before:Wang Ting Inventor before:Lu Chao Inventor before:Gu Haixia | |
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| TR01 | Transfer of patent right | Effective date of registration:20181226 Address after:518124 Office Building of Daya Bay Nuclear Power Base Engineering Company, Pengfei Road, Dapeng New District, Shenzhen City, Guangdong Province Co-patentee after:Shenzhen China Nuclear Power Design Co., Ltd. Patentee after:China Nuclear Power Engineering Co., Ltd. Co-patentee after:China General Nuclear Power Corporation Address before:518023 No. 69 Shennan Middle Road, Futian District, Shenzhen City, Guangdong Province Co-patentee before:China General Nuclear Power Corporation Patentee before:China Nuclear Power Engineering Co., Ltd. |