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Revisiting Insights from Three Mile Island Unit 2 Postaccident Examinations and Evaluations in View of the Fukushima Daiichi Accident

机译:鉴于福岛第一核电站事故,三英里岛2号机组事故后检查和评估的真知灼见

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摘要

The Three Mile Island Unit 2 (TMI-2) accident, which occurred on March 28, 1979, led industry and regulators to enhance strategies to protect against severe accidents in commercial nuclear power plants. Investigations in the years after the accident concluded that at least 45% of the core had melted and that nearly 19 tonnes of the core material had relocated to the lower head. Postaccident examinations indicate that about half of that material formed a solid layer near the lower head and above it was a layer of fragmented rubble. As discussed in this paper, numerous insights related to pressurized water reactor accident progression were gained from postaccident evaluations of debris, reactor pressure vessel (RPV) specimens, and nozzles taken from the RPV. In addition, information gleaned from TMI-2 specimen evaluations and available data from plant instrumentation were used to improve severe accident simulation models that form the technical basis for reactor safety evaluations. Finally, the TMI-2 accident led the nuclear community to dedicate considerable effort toward understanding severe accident phenomenology as well as the potential for containment failure. Because available data suggest that significant amounts of fuel heated to temperatures near melting, the events at Fukushima Daiichi Units 1, 2, and 3 offer an unexpected opportunity to gain similar understanding about boiling water reactor accident progression. To increase the international benefit from such an endeavor, we recommend that an international effort be initiated to (a) prioritize data needs; (b) identify techniques, samples, and sample evaluations needed to address each information need; and (c) help finance acquisition of the required data and conduct of the analyses.
机译:1979年3月28日发生的三英里岛2号机组(TMI-2)事故,导致行业和监管机构加强了防止商业核电厂发生严重事故的策略。事故发生后数年的调查得出结论,至少有45%的岩心已融化,将近19吨的岩心材料已转移到下端。事故后的检查表明,大约一半的材料在下部头部附近形成了一层固体,在其上方是一层碎石。如本文所述,从事后对碎片,反应堆压力容器(RPV)标本和从RPV取下的喷嘴的评估中,可以得出许多与压水堆事故进展相关的见解。此外,从TMI-2标本评估中收集的信息和来自工厂仪器的可用数据被用于改善严重事故模拟模型,这些模型构成了反应堆安全性评估的技术基础。最终,TMI-2事故导致核界付出了巨大的努力来了解严重的事故现象学以及安全壳失效的可能性。因为现有数据表明大量燃料被加热到接近融化的温度,所以福岛第一核电站1号,2号和3号机组的事件提供了意想不到的机会来获得对沸水反应堆事故进展的类似理解。为了从这种努力中获得国际利益,我们建议开始一项国际努力,以(a)优先处理数据需求; (b)确定解决每种信息需求所需的技术,样本和样本评估; (c)帮助资助所需数据的获取和分析的进行。

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  • 来源
    《Nuclear science and engineering》 |2012年第3期|p.223-248|共26页
  • 作者单位

    Idaho National Laboratory, Idaho Falls, Idaho;

    Argonne National Laboratory, Argonne, Illinois;

    University of Wisconsin-Madison, Madison, Wisconsin;

    Oak Ridge National Laboratory, Oak Ridge, Tennessee;

    Sandia National Laboratories, Albuquerque, New Mexico;

    Sandia National Laboratories, Albuquerque, New Mexico;

  • 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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