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Reactivity Feedback Effect on Supercritical Transient Analysis of Fuel Debris

机译:反应性反馈对燃料碎片超临界瞬态分析的影响

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摘要

Transient analysis for possible prompt supercritical accidents of fuel debris in the Fukushima Daiichi Nuclear Power Station is quite important. However, unlike solution fuel systems, there is little knowledge about supercritical transient analysis in fuel debris systems. In particular, reactivity feedback effects, which may have a significant impact on the results of the analysis, are important and require further study. In particular, the impacts of radiolysis gas void and moderator boiling should be discussed. Thus, the purpose of this study is to clarify whether the reactivity feedback effects of radiolysis gas and boiling of the moderator impact the supercritical transient analysis in fuel debris systems. To accomplish this, we used a power profile obtained by the MIK code with the Doppler reactivity feedback effect; radiolysis gas analysis and heat transfer analysis were performed. For the radiolysis gas analysis, the AGNES2 model was modified to consider the difference between solution fuel and fuel debris systems. The heat transfer analysis used an OpenFOAM solver to perform conjugate heat transfer calculations. We found that the radiolysis gas void was negligible when probable G values, which are the generation number of molecules per absorbed energy, were used. In addition, the results showed that boiling could be also negligible under most conditions. However, we found that the boiling time may be earlier than the peak time of the power when the radius of the fuel debris particle is small. In this case, ignoring the boiling may give conservative results. These considerations should be included in future analyses.
机译:暂停分析可能迅速迅速烟气核心核电站燃料碎片的超临界事故非常重要。然而,与解决方案燃料系统不同,关于燃料碎片系统中的超临界瞬态分析几乎没有了解。特别地,反应性反馈效果可能对分析结果产生重大影响,这是重要的并且需要进一步研究。特别地,应讨论放射性分解气体空隙和调节剂沸腾的影响。因此,本研究的目的是阐明放射性分解气体的反应性反馈效果是否对主持人的沸腾的反应性反馈效应是燃料碎片系统中的超临界瞬态分析。为此,我们使用了MIK码获得的功率配置文件,其中具有多普勒反应性反馈效果;进行辐射性分析气体分析和传热分析。对于放射性分析气体分析,修改酶2模型以考虑溶液燃料和燃料碎片系统之间的差异。传热分析使用OpenFoam求解器进行共轭传热计算。我们发现,当使用较可能的G值时,放射性分解气体空隙是可忽略不计的,这是每次吸收能量的分子的产生数量。此外,在大多数条件下,结果表明沸腾也可以忽略不计。然而,我们发现,当燃料碎片颗粒的半径很小时,沸点可能比功率的峰值时间更早。在这种情况下,忽略沸腾可能会提供保守的结果。这些考虑因素应包括在将来的分析中。

著录项

  • 来源
    《Nuclear science and engineering》 |2020年第7期|493-507|共15页
  • 作者单位

    Tokyo Institute of Technology Institute of Innovative Research Laboratory for Advanced Nuclear Energy Ookayama 2-12-1-N1-19 Meguro-ku Tokyo 152-8550 Japan;

    Tokyo Institute of Technology Institute of Innovative Research Laboratory for Advanced Nuclear Energy Ookayama 2-12-1-N1-19 Meguro-ku Tokyo 152-8550 Japan;

    Tokyo Institute of Technology Institute of Innovative Research Laboratory for Advanced Nuclear Energy Ookayama 2-12-1-N1-19 Meguro-ku Tokyo 152-8550 Japan;

  • 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

    Criticality safety; prompt supercritical kinetic analysis; radiolysis gas void; boiling; Fukushima Daiichi Nuclear Power Station decommissioning;

    机译:关键安全;迅速超临界动力学分析;放射性异液空隙;沸腾;Fukushima Daiichi核电站退役;
  • 入库时间 2022-08-18 21:23:42

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