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Verification of NETFLOW code using plant data of sodium cooled reactor and facility

机译:使用钠冷反应堆和设施的工厂数据验证NETFLOW代码

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摘要

The plant simulation code NETFLOW on PC applicable to the liquid-metal cooled reactors has been developed on the basis of the models developed for single-phase and two-phase light water flow systems. The functions of this code have been verified by individual tests for light water flow systems and a sodium flow system. In order to apply this code to a sodium cooled fast reactor, several extra functions were verified using the plant data obtained using 50 MW steam generators and the Monju fast breeder reactor. Finally, the turbine trip transient of the Monju was simulated and the result was compared with the measured plant data. Good agreements were obtained in these verifications. As a result of the present study, the code can be applied as an education tool for students.
机译:在为单相和两相轻水流量系统开发的模型的基础上,开发了适用于液态金属冷却反应堆的PC上的工厂仿真代码NETFLOW。该规范的功能已通过针对轻水流量系统和钠流量系统的单独测试进行了验证。为了将此代码应用于钠冷快堆,使用使用50兆瓦蒸汽发生器和Monju快中子增殖堆获得的工厂数据验证了几个附加功能。最后,对Monju的涡轮机跳闸瞬态进行了仿真,并将其结果与测得的工厂数据进行了比较。在这些验证中获得了良好的协议。作为本研究的结果,该代码可以用作学生的教育工具。

著录项

  • 来源
    《Nuclear Engineering and Design》 |2007年第1期|p.87-93|共7页
  • 作者

    Hiroyasu Mochizuki;

  • 作者单位

    Japan Atomic Energy Agency, 1 Shiraki, Tsuruga, Fukui 919-1279, Japan;

  • 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 原子能技术;
  • 关键词

  • 入库时间 2022-08-18 00:46:10

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