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A comparison of core degradation phenomena in the CORA,QUENCH,Phebus SFD and Phebus FP experiments

机译:在CORA,QUENCH,Phebus SFD和Phebus FP实验中岩心降解现象的比较

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摘要

Over the past 20 years, integral fuel bundle experiments performed at IRSN Cadarache, France (Phebus-SFD and Phebus FP - fission heated) and at Karlsruhe Institute of Technology, Germany (CORA and QUENCH - electrically heated), accompanied by separate-effect tests, have provided a wealth of detailed information on core degradation phenomena that occur under severe accident conditions, relevant to such safety issues as in-vessel retention of the core, recovery of the core by water reflood, hydrogen generation and fission product release. These data form an important basis for development and validation of severe accident analysis codes such as ASTEC (IRSN/GRS, EC) and MELCOR (USNRC/SNL, USA) that are used to assess the safety of current and future reactor designs, so helping to reduce the uncertainty associated with such code predictions. Following the recent end of the Phebus FP project, it is appropriate now to compare the core degradation phenomena observed in these four major experimental series, indicating the main conclusions that have been drawn. This covers subjects such as early phase degradation up to loss of rod-like geometry (all the series), late phase degradation and the link between fission product release and core degradation (Phebus FP), oxidation phenomena (all the series), reflood behaviour (CORA and QUENCH), as well as particular topics such as the effects of control rod material and fuel burn-up on core degradation. It also outlines the separate-effects experiments performed to elucidate specific phenomena such as the impact of chemical reactions involving boron carbide absorber material. Finally, it indicates the remaining topics for which further investigation is still required and/or is under way.
机译:在过去的20年中,在法国IRSN卡达拉奇(Phebus-SFD和Phebus FP-裂变加热)和德国卡尔斯鲁厄技术学院(CORA和QUENCH-电加热)进行了整体燃料束实验,并进行了单独的效果测试曾就严重事故条件下发生的堆芯退化现象提供了大量详细信息,这些信息与诸如堆芯在容器内的保留,通过注水回收堆芯,氢的产生和裂变产物释放等安全问题有关。这些数据为开发和验证严重事故分析代码(例如ASTEC(IRSN / GRS,EC)和MELCOR(USNRC / SNL,美国))奠定了重要基础,这些代码用于评估当前和未来反应堆设计的安全性,因此有助于以减少与此类代码预测相关的不确定性。在Phebus FP项目最近结束之后,现在比较一下在这四个主要实验系列中观察到的核心退化现象是合适的,这表明了已得出的主要结论。这涵盖了诸如从早期降解直至棒状几何形状丧失(所有系列),后期降解以及裂变产物释放与岩心降解(Phebus FP)之间的联系,氧化现象(所有系列)等主题。 (CORA和QUENCH),以及特定主题,例如控制杆材料和燃料燃烧对堆芯退化的影响。它还概述了为阐明特定现象(例如涉及碳化硼吸收剂材料的化学反应的影响)而进行的单独效果实验。最后,它指出仍需要和/或正在进行进一步调查的其余主题。

著录项

  • 来源
    《Nuclear Engineering and Design》 |2015年第3期|8-20|共13页
  • 作者单位

    Institut de Radioprotection et de Surete Nucleaire (IRSN), PSN-RES/SAG/LETR Bat 702, BP 3, F-13115 St. Paul-lez-Durance Cedex, France;

    Karlsruhe Institute of Technology (KIT), Hermann-von-Helmholtz-Platz 1, D-76344 Eggenstein-Leopoldshafen, Germany;

    Institut de Radioprotection et de Surete Nucleaire, IRSN, BP 3, F-13115 St. Paul-lez-Durance Cedex, France;

    Institut de Radioprotection et de Surete Nucleaire, IRSN, BP 3, F-13115 St. Paul-lez-Durance Cedex, France;

    Karlsruhe Institute of Technology (KIT), Hermann-von-Helmholtz-Platz 1, D-76344 Eggenstein-Leopoldshafen, Germany;

    Karlsruhe Institute of Technology (KIT), Hermann-von-Helmholtz-Platz 1, D-76344 Eggenstein-Leopoldshafen, Germany;

  • 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

  • 入库时间 2022-08-18 00:42:15

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