Study on the Disturbances Analysis System for Nuclear Power Plant

核电厂扰动分析系统的研究

• 批准号: 60460234
• 负责人: WAKABAYASHI Jiro
• 金额: $ 2.69万
• 依托单位: Kyoto University
• 依托单位国家: 日本
• 项目类别: Grant-in-Aid for General Scientific Research (B)
• 财政年份: 1985
• 资助国家: 日本
• 起止时间: 1985 至 1987
• 项目状态: 已结题
• 来源: https://kaken.nii.ac.jp/en/grant/KAKENHI-PROJECT-60460234/
• 关键词: Identification of multiple disturbances; On-line estimation of sefety parameters; Accident tracking simulator; 蒸気発生器細管破断; 安全パラメータ; 実時間事故追跡; AIマネジャーシステム; 加圧水型原子炉; 観測信号; 負荷追従運転; 異常外乱推定

This research has been continued from before 1985.1) We developed the identification method of multiple disturbances happened in Nuclear Power Plant (NPP), where projective operator method was applied to the plant instrumentation signals. By the development of new data processing methods, the above method was extended to be applicable not only for the approximately linear plant (BWR) but also for the remarkable non-linear plant (PWR) and for the plant operated with automatic frequency control (AFC).2) We developed the on-line real-time estimation method of safety parameters for post small break loss of coolant accident (SBLOCA) PWR Plant. i.e. a) break size and break location for pipe break, b) break flow rate from primary side to secondary side for steam generator (SG) tube rupture, and c) heat transfer rate from primary side to secondary side of SG.3) We developed the real-time accident tracking simulation code, TOKRAC, where the real-time estimated signals and several plant instrumentation signals are utilized as input signals. The validity of this tracking simulator was examined by the computer experiments for TM@i-2 accident, SBLOCA of Westinghouse type PWR plant and Prairie Island-1 accident.4) We propose an AI manager system for the effective intergration of the safety parameters estimation method and accident tracking simulator. This system has following functions; a) accident detection and identification of the type of SBLOCA, b) management of accident tracking calculation and c) timely display of qualified informations.

从1985.1）进行了这项研究，我们开发了多种干扰的识别方法发生在核电站（NPP）中，该方法将投射操作员方法应用于工厂仪器信号。通过开发新的数据处理方法，上述方法不仅适用于大约线性工厂（BWR），而且适用于非线性植物（PWR）以及使用自动频率控制（AFC）操作的工厂（AFC） ）.2）我们开发了在线实时估计方法的安全参数方法，用于在冷却剂事故（SBLOCA）PWR植物的小中断损失。即a）管道断裂的断裂尺寸和断裂位置，b）从初级侧到蒸汽发生器（SG）管破裂的次要侧的断裂流量，c）从SG.3的初级侧到次级的传热速率）我们开发了实时事故跟踪仿真代码Tokrac，该代码TOKRAC，在该代码中，将实时估计的信号和几个工厂仪器信号用作输入信号。通过计算机实验进行TM@I-2事故，Westinghouse Type Pwr Plant和Prairie Island-1事故的计算机实验检查了此跟踪模拟器的有效性。4）我们提出了一个AI Manager系统，以有效地相互介入安全参数估算方法和事故跟踪模拟器。该系统具有以下功能； a）事故检测和识别SBLOCA类型，b）事故跟踪计算的管理和c）及时显示合格信息。

项目成果

若林二郎: Proc. International Conference on Man-Machine Interface in the Muclear Industry, IAEA-CN-49/16. (1986)

若林次郎：核工业人机界面国际会议，IAEA-CN-49/16 (1986)。

五福明夫: Proc. 6th Power Plant Dynamics, Control and Testing Symposium Univ. fo Tenessee. 2. 67-1 (1986)

Akio Gofuku：田纳西大学第六届发电厂动力学、控制和测试研讨会。

Gofuku,Akio: "Study on the Diagnostic Techonique of Small Break Loss of Coolant Accident of PWR Plant" Nuclear Technology (Journal of American Nuclear Society). 81. (1988)

Gofuku，Akio：“压水堆核电站冷却剂事故小断损诊断技术研究”核技术（美国核学会杂志）。

若林二郎: Nuclear Techonology(Journal of American Nurlear Society). 70. 343-353 (1986)

若林二郎：核技术（美国核学会杂志）。70. 343-353 (1986)。

吉川栄和: Proc.2nd International Topical Meeting on Nuclear Power Plant Thermal Hydraulics and Operations. 8,17-24 (1986)

Eikazu Yoshikawa：Proc.2nd 国际核电站热工水力学和运行专题会议 8,17-24 (1986)。