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首页> 外文期刊>Nuclear Technology >A Core Physics Study of Advanced Sodium-Cooled TRU Burners with Thorium- and Uranium-Based Metallic Fuels
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A Core Physics Study of Advanced Sodium-Cooled TRU Burners with Thorium- and Uranium-Based Metallic Fuels

机译:含Thor和铀基金属燃料的先进钠冷TRU燃烧器的核心物理研究

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摘要

In this work, 400-MW(electric) sodium-cooled fast reactor cores using thorium- and uranium-based metallic fuels for high burning rates of light water reactor spent-fuel transuranics (TRUs) are neutronically designed and analyzed based on equilibrium cycles with a focus on consistent comparative analysis of the differences in performance between thorium- and uranium-based fueled cores. Axial uranium and thorium blankets are introduced in thorium- and uranium-based driver fueled burner cores to improve TRU burning rates without considerable increases of burnup reactivity swing. For this core configuration, it was shown that cores using thorium and depleted uranium blankets can be designed to have a high TRU burning rate, a low sodium void reactivity (SVR) worth, and a low burnup reactivity swing. In particular, the use of uranium or thorium blankets without recycling in the thorium-based driver fueled cores led to significant reductions of burnup reactivity swing with considerable increases of the TRU burning rate and small increases of SVR. In addition, the core configuration having central nonfuel regions was considered to show the effects of the thorium-based driver metallic fuel versus the uranium-based metallic fuel coupled with moderator rods. The core configuration with thorium-based fuel led to a negative SVR without moderator rods, and the use of moderator rods further improved the Doppler coefficient and reduced SVR. Also, a decomposition analysis of SVR was performed to better understand the differences in the contributing factors between the uranium- and thorium-based fueled cores, and a quasi-static reactivity balance analysis was performed to show the inherent safety of the cores in terms of self-controllability.
机译:在这项工作中,对基于th和铀基金属燃料以高燃烧率的轻水反应堆乏燃料超铀燃料(TRU)的400兆瓦(电)钠冷却快堆堆芯进行了中子设计,并根据平衡循环进行了分析。重点是对comparative和铀基燃料芯之间性能差异进行一致的比较分析。轴向铀和driver毯被引入th和铀基驱动燃料燃烧器芯中,以提高TRU燃烧速率,而不会显着增加燃耗反应性摆幅。对于这种核心构型,已证明可以将使用and和贫铀覆盖层的核心设计为具有较高的TRU燃烧速率,较低的钠空隙反应性(SVR)值和较低的燃耗反应性波动。特别是,在基于without的驱动器燃料芯中使用没有回收的铀或th毯,可显着降低燃耗反应性波动,同时显着提高TRU燃烧速率和SVR小幅增长。另外,具有中心非燃料区域的芯构型被认为显示了based基驱动金属燃料相对于铀基金属燃料与减速杆的耦合作用。含fuel基燃料的核心配置导致没有减速杆的SVR为负值,减速杆的使用进一步提高了多普勒系数并降低了SVR。另外,对SVR进行了分解分析,以更好地理解铀和th基燃料芯之间的贡献因素之间的差异,并进行了准静态反应性平衡分析,以显示芯的固有安全性。自控能力。

著录项

  • 来源
    《Nuclear Technology》 |2016年第2期|217-232|共16页
  • 作者

    Wuseung You; Ser Gi Hong;

  • 作者单位

    Kyung Hee University, Department of Nuclear Engineering, Deogyeong-daero, Giheung-gu, Yongin, Gyeonggi-do 446-701, Korea;

    Kyung Hee University, Department of Nuclear Engineering, Deogyeong-daero, Giheung-gu, Yongin, Gyeonggi-do 446-701, Korea;

  • 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

    Sodium-cooled fast reactor; TRU burning; thorium fuel;

    机译:钠冷快堆;TRU燃烧;fuel燃料;

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