摘要：【中文】本发明公开了一种含缺陷管道破损安全期的评估系统及方法。所述系统包括：计算程序，用于管道缺陷扩展分析计算以及含缺陷管道的最终评估等；系统数据库，用于保存运行参数、裂纹初始缺陷尺寸、关注管道部位的历史载荷谱、管部件几何参数、材料属性等数据；系统硬件，用于支撑上述计算程序和数据库的运行。本系统对核电厂管道缺陷危害潜在风险较大的管道回路进行跟踪监测，以获得含缺陷管道的承载状态，用于分析评估管道回路可安全运行的期限，同时可以完成时限老化分析评估(TLAA)；此外针对核电厂安全壳内含缺陷的高能管道，还可进行破裂排除的分析评估。 【EN】The invention discloses a system and a method for evaluating the damage safety period of a pipeline with defects. The system comprises: the calculation program is used for the expansion analysis calculation of the pipeline defects, the final evaluation of the pipelines containing the defects and the like; the system database is used for storing data such as operation parameters, initial crack defect sizes, historical load spectrums of concerned pipeline parts, geometric parameters of pipe parts, material attributes and the like; and the system hardware is used for supporting the operation of the calculation program and the database. The system tracks and monitors a pipeline loop with a large potential risk of damage caused by the defect of the nuclear power plant pipeline to obtain the bearing state of the pipeline with the defect, is used for analyzing and evaluating the safe operation time limit of the pipeline loop, and can complete time limit aging analysis and evaluation (TLAA); in addition, the analysis and evaluation of the crack exclusion can be carried out aiming at the high-energy pipeline containing the defects in the containment vessel of the nuclear power plant.

摘要：【中文】本发明公开了核电厂疲劳监测和寿命评估系统的瞬态温度场计算方法，通过系统接口从电厂数据库读入电厂数字化控制系统采集的一回路系统流体温度数据T_w(t)，作为瞬态温度场计算的输入，通过温度场方程计算圆柱壳体或球壳体的内壁面温度瞬态，作为后续热应力计算的输入。优点在于：本发明适用于核电厂设备和管道的瞬态温度场求解方法，该方法采用圆柱壳体或球壳体的瞬态温度场方程，利用一回路系统流体温度数据快速的计算瞬态温度场，该方法不需要结构壁面温度作为计算输入，从而无需在一回路设备或管道的外壁面增加温度测量仪表，减少了疲劳监测系统对电厂设计和现场布置的影响，降低了系统的施工和维护成本。 【EN】The invention discloses a transient temperature field calculation method for a nuclear power plant fatigue monitoring and life evaluation system, which reads primary loop system fluid temperature data T acquired by a digital control system of a power plant from a power plant database through a system interface_wAnd (t) as the input of transient temperature field calculation, calculating the temperature transient of the inner wall surface of the cylindrical shell or the spherical shell through a temperature field equation, and taking the temperature transient as the input of subsequent thermal stress calculation. Has the advantages that: the invention is suitable for solving the transient temperature field of nuclear power plant equipment and pipelines, and adopts the transient temperature field of a cylindrical shell or a spherical shellThe method does not need to take the temperature of the structural wall surface as calculation input, so that a temperature measuring instrument does not need to be added on the outer wall surface of loop equipment or a pipeline, the influence of a fatigue monitoring system on the design and field arrangement of a power plant is reduced, and the construction and maintenance cost of the system is reduced.

摘要：【中文】本发明公开了一种核电厂疲劳监测和寿命评估系统，包括系统硬件、系统平台、计算程序、系统数据库，所述系统硬件由系统服务器、数据库服务器、备份服务器、网络交换机组成，所述系统平台由人机交互界面和系统管理服务系统组成，所述系统管理服务由数据采集、数据存储、数据处理、参数显示、数据检索、趋势显示、报表制定、参考资料、系统管理组成，所述计算程序由测点筛选、NCR()评估、温度场解析解、应力场解析解以及测试验证组成。本发明的监测范围广，覆盖核岛一回路全部主设备、主要管道，系统创新的实现了“不增加硬件仪表测点”，通过模型推导的方法，来获得关注位置的温度状态，这样确保了老电厂在应用时，最小的改造和最高的效率。系统创新的考虑了压水堆冷却剂环境对金属疲劳的影响，满足核安全局对电厂装料许可证的要求。 【EN】The invention discloses a fatigue monitoring and service life evaluation system for a nuclear power plant, which comprises system hardware, a system platform, a calculation program and a system database, wherein the system hardware consists of a system server, a database server, a backup server and a network switch, the system platform consists of a human-computer interaction interface and a system management service system, the system management service consists of data acquisition, data storage, data processing, parameter display, data retrieval, trend display, report formulation, reference data and system management, and the calculation program consists of measurement point screening, NCR () evaluation, temperature field analytic solution, stress field analytic solution and test verification. The invention has wide monitoring range, covers all main equipment and main pipelines of a loop of the nuclear island, innovatively realizes that the temperature state of a concerned position is obtained by a model derivation method without adding hardware instrument measuring points, thereby ensuring the minimum reconstruction and the highest efficiency of an old power plant when in application. The system innovatively considers the influence of the pressurized water reactor coolant environment on metal fatigue, and meets the requirement of a nuclear safety bureau on the charging license of a power plant.

摘要：【中文】一种跳线体系风偏响应的风洞试验测试装置，包括跳线体系、风洞实验装置、非接触式位移测试装置及数据处理系统；所述跳线体系包括绝缘子串、跳线、连接金具及线夹，绝缘子串的一端通过连接金具垂直设置在所述风洞实验装置的顶部内壁上，绝缘子串的另一端通过连接金具及线夹与跳线连接，跳线的两端可拆卸式设置在风洞实验装置的相对侧壁上；非接触式位移测试装置包括标靶、视频采集装置及视频数据处理装置，所述标靶设置在所述线夹上，视频采集装置固定设置于风洞实验装置的风洞外并通过风洞实验装置侧壁上的透明玻璃窗对标靶进行动态位移测试，视频数据处理装置与所述视频采集装置数据连接，所述数据处理系统与所述视频数据处理装置数据连接。 【EN】A wind tunnel test device for wind deflection response of a jumper system comprises the jumper system, a wind tunnel test device, a non-contact displacement test device and a data processing system; the jumper system comprises an insulator string, a jumper, a connecting hardware fitting and a wire clamp, wherein one end of the insulator string is vertically arranged on the inner wall of the top of the wind tunnel experiment device through the connecting hardware fitting, the other end of the insulator string is connected with the jumper through the connecting hardware fitting and the wire clamp, and two ends of the jumper are detachably arranged on opposite side walls of the wind tunnel experiment device; the non-contact displacement testing device comprises a target, a video acquisition device and a video data processing device, wherein the target is arranged on the wire clamp, the video acquisition device is fixedly arranged outside a wind tunnel of the wind tunnel experiment device and is used for carrying out dynamic displacement testing on the target through a transparent glass window on the side wall of the wind tunnel experiment device, the video data processing device is in data connection with the video acquisition device, and the data processing system is in data connection with the video data processing device.

摘要：【中文】本发明的目的在于公开一种核电厂支持疲劳监测功能的瞬态监测方法，通过核电厂仪控系统原有仪表的实时测量数据自动识别发生在监测对象上的瞬态开始与结束，并归纳已识别瞬态的特征参数；同时依据数据库实现：①通过特征参数的比对，判别已识别瞬态属于该监测对象或其所属工艺系统预期的瞬态类别，记录瞬态类别、发生次数与发生时间，通过已记录的瞬态类别直接从数据库中获得相对应的监测对象的应力变化时程；②若已识别瞬态不属于数据库中任何已有类别的瞬态，则根据已识别瞬态的特征参数在数据库中建立新瞬态类别，通过分析计算获得该瞬态类别作用下的监测对象应力变化时程，并存入数据库的新瞬态类别中，支持后续完成对监测对象的疲劳损伤评估。 【EN】The invention aims to disclose a transient monitoring method for supporting a fatigue monitoring function of a nuclear power plant, which automatically identifies the beginning and the end of a transient occurring on a monitored object through real-time measurement data of an original instrument of an instrument control system of the nuclear power plant, and induces characteristic parameters of the identified transient, and is realized according to a database, wherein ① judges that the identified transient belongs to the transient type expected by the monitored object or a process system to which the monitored object belongs through the comparison of the characteristic parameters, records the transient type, the occurrence frequency and the occurrence time, directly obtains the stress change time interval of the corresponding monitored object from the database through the recorded transient type, and ② establishes a new transient type in the database according to the characteristic parameters of the identified transient if the identified transient does not belong to any existing type of the database, obtains the stress change time interval of the monitored object under the action of the transient type through analysis and calculation, and stores the stress change time interval into the new transient type of the database, thereby supporting the subsequent completion of fatigue damage assessment of the monitored object.

摘要：【中文】本发明公开了一种核电厂运维关键数据请求和处理系统，包括系统架构，所述系统架构支持B/S架构和C/S架构，其中数据通信接口基于数据源接口系统的API，适用于在数据源发生变化时通过更新API函数，其中系统硬件通过网络设备接入核电厂局域网，其中局域网内的办公电脑、工作站均以客户端访问系统，所述系统架构仅包含若干服务器，所述其中服务器适用于接入任意局域网后经网络配置后即可用，所述系统架构内设置有数据采集、数据预处理和数据存储。本发明系统不与电厂DCS直接接口，不影响生产网络安全，通过电厂局域网内数据源获取数据，在电厂局域网故障缺失数据时，通过系统的数据补录模块离线的补录数据。 【EN】The invention discloses a nuclear power plant operation and maintenance key data request and processing system which comprises a system architecture, wherein the system architecture supports a B/S architecture and a C/S architecture, a data communication interface is based on an API of a data source interface system and is suitable for updating an API function when a data source changes, system hardware is accessed to a nuclear power plant local area network through network equipment, office computers and workstations in the local area network access the system through clients, the system architecture only comprises a plurality of servers, the servers are suitable for being used after being accessed to any local area network and being configured through a network, and data acquisition, data preprocessing and data storage are arranged in the system architecture. The system of the invention does not directly interface with the power plant DCS, does not affect the production network safety, obtains data through a data source in the power plant LAN, and supplements data offline through a data supplementation module of the system when the power plant LAN fails and lacks data.