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Development and primary verification of a transient analysis software for high temperature gas-cooled reactor helium turbine power system

机译:高温气冷堆氦涡轮发电系统瞬态分析软件的开发和初步验证

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摘要

The transient analysis software, HTR-GTsim, is developed to simulate transient characteristics of a high temperature gas-cooled reactor helium turbine power system (HTR-10GT) of INET inTsinghua University, which is the secondary engineering project of HTR-10. The analysis models include point reactor neutron kinetics model, one-dimensional thermodynamic reactor model, rotor dynamic blower model, counter-current heat exchanger model, quasi-static helium turbine and pressure compressor model, and so on. HTR-GTsim is verified by 3 tests of a 10MW high temperature gas-cooled reactor (HTR-10), which are reactivity insertion test, helium flow change test and water flow change test. The simulation results of reactivity insertion test show that there is a strong self-adjusting ability for HTR-10 reactor power due to negative temperature feedback. The simulation results of helium flow change test are compared with those of the water flow change test. It is found that the disturbance induced in the latter test is significantly weaker than that in the former due to the huge heat capacity of the graphite in the core. The calculation results of HTR-GTsim are compared with the test data and simulation results of THERMIX program. Good agreement is obtained. Because of the limitation of validation, more work need to be done to verify the accuracy of HTR-GTsim to simulate a gas turbine device.
机译:开发了瞬态分析软件HTR-GTsim来模拟清华大学INET的高温气冷堆氦气涡轮动力系统(HTR-10GT)的瞬态特性,这是HTR-10的二次工程。分析模型包括点反应堆中子动力学模型,一维热力学反应堆模型,转子动态鼓风机模型,逆流热交换器模型,准静态氦轮机和压力压缩机模型等。 HTR-GTsim通过10MW高温气冷堆(HTR-10)的3个测试进行了验证,这些测试是反应性插入测试,氦流量变化测试和水流量变化测试。反应性插入试验的仿真结果表明,由于温度反馈为负,因此HTR-10反应堆功率具有很强的自我调节能力。将氦流量变化测试的模拟结果与水流量变化测试的模拟结果进行了比较。发现由于芯中石墨的巨大的热容量,在后一种测试中引起的扰动明显弱于前一种。将HTR-GTsim的计算结果与THERMIX程序的测试数据和仿真结果进行比较。获得良好的协议。由于验证的局限性,需要做更多的工作来验证HTR-GTsim模拟燃气轮机设备的准确性。

著录项

  • 来源
    《Nuclear Engineering and Design》 |2012年第9期|p.219-228|共10页
  • 作者单位

    Institute of Nuclear and New Energy Technology, Tsinghua University, Beijing 100084, PR China;

    Institute of Nuclear and New Energy Technology, Tsinghua University, Beijing 100084, PR China;

    Institute of Nuclear and New Energy Technology, Tsinghua University, Beijing 100084, PR China;

    Institute of Nuclear and New Energy Technology, Tsinghua University, Beijing 100084, PR 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
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