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Engineered safeguards systems and method in nuclear power plant training simulator

机译:核电站培训模拟器中的工程保障系统和方法

摘要

A method and system for simulating the dynamic real-time operation of a nuclear power plant wherein a plurality of remote control devices provide input data to a digital computer to calculate physical values corresponding to plant operation to operate indicating devices for monitoring the physical operation of the plant.PPThe simulation includes an electrical network calculation technique for solving a complex fluid flow network whereby non-linearity is applied by coefficient variation at subsequent time steps. Several engineered safeguards systems, including the accumulator system is disclosed. The safety injection system simulation is further characterized by a different network for each path that can be utilized in operation. The residual heat removal system is modeled to provide a path through each of the heat exchangers including the bypass around pumps for warming up pumps during start-up. The simulation of boron regulation in the reactor includes a fast rate of boration, a slow rate of deboration and uniform boration in the reactor and is characterized by modeling the boration for reactor and entire reactor coolant loop as one tank, with delay incorporated into the boration at the rector portion for indicating the delays in the boric acid input of the safety injection system. The chemical and volume control system simulation is characterized by several functional subdivisions for letdown and charging. The seal flow system for reactor coolant pumps incorporates in the simulation time delays caused by temperature changes during reverse flow through pump seals. The component cooling system simulation is characterized by several continuous flow loops with the amount of surge flow dependent on change of density of the component cooling water.
机译:一种用于模拟核电站的动态实时运行的方法和系统,其中多个远程控制设备将输入数据提供给数字计算机,以计算与工厂运行相对应的物理值,从而运行指示装置,以监视核电厂的物理运行。

该模拟包括用于解决复杂流体流动网络的电网计算技术,由此通过在随后的时间步长处的系数变化来应用非线性。公开了几种工程保障系统,包括蓄能器系统。安全注入系统仿真的特征还在于,可以在操作中使用的每个路径都有不同的网络。对残留热量去除系统进行建模,以提供一条通过每个热交换器的路径,包括绕过泵的旁路,以便在启动过程中对泵进行预热。反应堆中硼调节的模拟包括快速的硼酸化速率,缓慢的脱硼速率和反应器中的均匀硼酸化,其特征在于将反应器的硼酸化和整个反应堆冷却剂环路建模为一个罐,并在硼酸化中引入延迟在调节器部分上的箭头指示安全注射系统的硼酸输入延迟。化学和体积控制系统仿真的特点是对卸料和装料进行了几个功能细分。用于反应堆冷却剂泵的密封流系统将模拟时间延迟纳入其中,该时间延迟是由于在通过泵密封的反向流动期间温度变化而引起的。组件冷却系统模拟的特征是几个连续的流动回路,其浪涌流量取决于组件冷却水的密度变化。

著录项

  • 公开/公告号US4064392A

    专利类型

  • 公开/公告日1977-12-20

    原文格式PDF

  • 申请/专利权人 WESTINGHOUSE ELECTRIC CORPORATION;

    申请/专利号US19740519723

  • 发明设计人 ADEWUNMI A. DESALU;

    申请日1974-10-31

  • 分类号G06F15/52;

  • 国家 US

  • 入库时间 2022-08-22 21:33:47

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