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Development and Application of an Engineering Simulator for HTR-PM Using THERMIX/BLAST and vPower

机译:使用THERMIX / BLAST和vPower的HTR-PM工程仿真器的开发和应用

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摘要

Different from most current commercial nuclear power plants, the High-Temperature gas-cooled Reactor Pebble-bed Module (HTR-PM) power plant consists of two reactor modules connected to a common steam turbine system that will bring a special coupling effect between the two reactor modules. An engineering simulator of the HTR-PM plant was developed by embedding the THERMIX/BLAST code into the vPower simulation platform. Two sets of nuclear steam supply systems of HTR-PM, including two reactors, two steam generators, two helium blowers, and the helium flow ducts, were simulated by two THERMIX/BLAST code modules, respectively. The entire secondary loop system was simulated using intrinsic models of the vPower simulation platform. The vPower platform connects and synchronizes the two THERMIX/BLAST modules, as well as the simulation module for the secondary loop system. The engineering simulator was applied to simulate the behavior of HTR-PM under steady-state operation, startup and shutdown processes, and accident conditions. The coupling effect during the condition conversion process and the thermal characteristics under accident conditions of HTR-PM were analyzed by the engineering simulator.
机译:与大多数目前的商业核电站不同,高温气冷堆卵石床模块(HTR-PM)电站由两个反应堆模块组成,这些模块连接到一个通用的蒸汽轮机系统,这将在两者之间带来特殊的耦合效果反应堆模块。通过将THERMIX / BLAST代码嵌入vPower仿真平台,开发了HTR-PM工厂的工程仿真器。通过两个THERMIX / BLAST代码模块分别模拟了两组HTR-PM的核蒸汽供应系统,包括两个反应堆,两个蒸汽发生器,两个氦气鼓风机和氦气流道。使用vPower仿真平台的固有模型对整个次级回路系统进行了仿真。 vPower平台连接并同步了两个THERMIX / BLAST模块以及辅助回路系统的模拟模块。工程仿真器用于模拟HTR-PM在稳态操作,启动和关闭过程以及事故情况下的行为。通过工程仿真器分析了条件转换过程中的耦合效应和HTR-PM事故条件下的热特性。

著录项

  • 来源
    《Nuclear Technology》 |2017年第1期|27-44|共18页
  • 作者单位

    Tsinghua University, Institute of Nuclear and New Energy Technology, Collaborative Innovation Center of Advanced Nuclear Energy Technology, Key Laboratory of Advanced Reactor Engineering and Safety, Ministry Education, Beijing 100084, China;

    Tsinghua University, Institute of Nuclear and New Energy Technology, Collaborative Innovation Center of Advanced Nuclear Energy Technology, Key Laboratory of Advanced Reactor Engineering and Safety, Ministry Education, Beijing 100084, China;

    Tsinghua University, Institute of Nuclear and New Energy Technology, Collaborative Innovation Center of Advanced Nuclear Energy Technology, Key Laboratory of Advanced Reactor Engineering and Safety, Ministry Education, Beijing 100084, China;

    Tsinghua University, Institute of Nuclear and New Energy Technology, Collaborative Innovation Center of Advanced Nuclear Energy Technology, Key Laboratory of Advanced Reactor Engineering and Safety, Ministry Education, Beijing 100084, China;

  • 收录信息 美国《科学引文索引》(SCI);美国《工程索引》(EI);美国《生物学医学文摘》(MEDLINE);
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

    Engineering simulator; HTR-PM; THERMIX/BLAST;

    机译:工程仿真器;HTR-PM;THERMIX / BLAST;
  • 入库时间 2022-08-18 00:42:46

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