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Sensitivity studies of modular high-temperature gas-cooled reactor postulated accidents

机译:模块化高温气冷堆假定事故的敏感性研究

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摘要

The results of various accident scenario simulations for the two major modular high temperature gas-cooled reactor (HTGR) variants (prismatic and pebble bed cores) are presented. Sensitivity studies can help to quantify the uncertainty ranges of the predicted outcomes for variations in some of the more crucial system parameters, as well as for occurrences of equipment and/or operator failures or errors. In addition, sensitivity studies can guide further efforts in improving the design and determining where more (or less) R&D is appropriate. Both of the modular HTGR designs studied - the 400-MW(t) pebble bed modular reactor (PBMR, pebble) and the 600-MW(t) gas-turbine modular helium reactor (GT-MHR, prismatic) - show excellent accident prevention and mitigation capabilities because of their inherent passive safety features. The large thermal margins between operating and "potential damage" temperatures, along with the typically very slow accident response times (approximate days to reach peak temperatures), tend to reduce concerns about uncertainties in the simulation models, the initiating events, and the equipment and operator responses.
机译:给出了两种主要的模块化高温气冷堆(HTGR)变体(棱柱和卵石床堆芯)的各种事故情景模拟的结果。敏感性研究可以帮助量化一些更关键的系统参数的变化以及设备和/或操作员的故障或错误发生的预期结果的不确定范围。此外,敏感性研究可以指导进一步的工作,以改进设计并确定更多(或更少)研发的位置。所研究的两种模块化HTGR设计-400兆瓦(t)卵石床模块化反应堆(PBMR,卵石)和600兆瓦(t)燃气轮机模块化氦反应堆(GT-MHR,棱柱形)-表现出出色的事故预防和缓解功能,因为其固有的被动安全功能。运行温度和“潜在损坏”温度之间的较大热裕度,以及通常非常缓慢的事故响应时间(达到峰值温度大约需要几天),往往会减少对模拟模型,启动事件以及设备和设备的不确定性的担忧。操作员的响应。

著录项

  • 来源
    《Nuclear Engineering and Design》 |2006年第6期|p.454-462|共9页
  • 作者

    Syd Ball;

  • 作者单位

    Nuclear Science & Technology Division, Oak Ridge National Laboratory, P.O. Box 2008, Oak Ridge, TN 37831-6010, USA;

  • 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

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