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首页> 外文期刊>Atomic Energy >UNANTICIPATED LARGE-DIAMETER PIPE RUPTURE ACCIDENTS IN THE RBMK-1000 CIRCULATION LOOP WITH REACTOR EMERGENCY COOLING SYSTEM FAILURE
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UNANTICIPATED LARGE-DIAMETER PIPE RUPTURE ACCIDENTS IN THE RBMK-1000 CIRCULATION LOOP WITH REACTOR EMERGENCY COOLING SYSTEM FAILURE

机译:RBMK-1000循环回路中意外的大直径管道破裂事故,反应器紧急冷却系统故障

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摘要

The results of calculations of large-diameter pipe rupture accidents in the RBMK circulation loop (pressure header of the main circulation pump, down pipe of the steam drum, and distribution group header) with failure of the reactor emergency cooling system are presented. The main computational problem is to evaluate the onset time of fuel-element cladding depressurization in the damaged half of the core and the integrity of the channel tubes. It is shown that for rupture of the pressure header fuel-element cladding depressurization starts at the 10th minute after the initial event and depressurization of the down-pipe near the steam drum and distribution group header start at the 17th and 40th minutes, respectively. The possible rupture of the channel tubes can have the form of only individual small flaws, for which the structural integrity of the reactor space is preserved. The calculations were performed with the RELAP5/mod3.2 computer code adapted for RBMK.
机译:给出了带有反应堆应急冷却系统故障的RBMK循环回路(主循环泵的压力总管,蒸汽鼓的下行管和分配组总管)中大直径管道破裂事故的计算结果。主要的计算问题是评估芯部受损半部中燃料元件包壳降压的开始时间以及通道管的完整性。结果表明,对于压力总管破裂,在初始事件发生后的第10分钟开始降压,而在汽包和分配组总管附近的下水管降压分别在第17和40分钟开始。通道管的可能破裂可以仅具有单个小缺陷的形式,为此保留了反应器空间的结构完整性。使用适用于RBMK的RELAP5 / mod3.2计算机代码进行计算。

著录项

  • 来源
    《Atomic Energy》 |2013年第1期|1-4|共4页
  • 作者

    Yu. M. Nikitin; V. E. Gmyrko;

  • 作者单位

    Dollezhal Research and Development Institute of Power Engineering (NIKIET), Moscow;

    Rosatom State Corporation, Moscow;

  • 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

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