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Ultra-High Temperature Reactor Experiment (UHTREX) Transients

机译:超高温反应堆实验(UHTREX)瞬态

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摘要

Three types of transients in the UHTREX reactor have been numerically evaluated. They are (1) withdrawal of one plug rod at the design speed of 18 in./min starting from near zero power, (2) withdrawal of one plug rod at 18 in./min starting from 3 MW delayed critical, and (3) scrams from 3 MW delayed critical. None of these transients would result in serious damage to the reactor, although in case 2 fuel particle melting occurs if a power scram does not terminate the excursion. Also, stressing of the fuel elements may be significant in case 1.

著录项

  • 作者

    John C. Vigil;

  • 作者单位
  • 年度 1967
  • 页码 1-27
  • 总页数 27
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类 工业技术;
  • 关键词

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