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Composite nuclear fuel fabrication methodology for gas fast reactors.

机译:燃气快堆的复合核燃料制造方法。

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摘要

An advanced fuel form for use in Gas Fast Reactors (GFR) was investigated. Criteria for the fuel includes operation at high temperature (∼1400°C) and high burnup (∼150 MWD/MTHM) with effective retention of fission products even during transient temperatures exceeding 1600°C. The GFR fuel is expected to contain up to 20% transuranics for a closed fuel cycle. Earlier evaluations of reference fuels for the GFR have included ceramic-ceramic (cercer) dispersion type composite fuels of mixed carbide or nitride microspheres coated with SiC in a SiC matrix. Studies have indicated that ZrC is a potential replacement for SiC on account of its higher melting point, increased fission product corrosion resistance and better chemical stability. The present work investigated natural uranium carbide microspheres in a ZrC matrix instead of SiC.;Known issues of minor actinide volatility during traditional fabrication procedures necessitated the investigation of still high temperature but more rapid fabrication techniques to minimize these anticipated losses. In this regard, fabrication of ZrC matrix by combustion synthesis from zirconium and graphite powders was studied. Criteria were established to obtain sufficient matrix density with UC microsphere volume fractions up to 30%. Tests involving production of microspheres by spark erosion method (similar to electrodischarge machining) showed the inability of the method to produce UC microspheres in the desired range of 300 to 1200 mum. A rotating electrode device was developed using a minimum current of 80A and rotating at speeds up to 1500 rpm to fabricate microspheres between 355 and 1200 mum. Using the ZrC process knowledge, UC electrodes were fabricated and studied for use in the rotating electrode device to produce UC microspheres. Fabrication of the cercer composite form was studied using microsphere volume fractions of 10%, 20%, and 30%. The macrostructure of the composite and individual components at various stages were characterized to understand the required fabrication techniques and at the same time meet the necessary GFR fuel characteristics.
机译:研究了用于气体快速反应堆(GFR)的先进燃料形式。燃料的标准包括在高温(〜1400°C)和高燃耗(〜150 MWD / MTHM)下运行,即使在超过1600°C的瞬态温度下也能有效保留裂变产物。对于封闭的燃料循环,GFR燃料预计将包含高达20%的超铀化合物。用于GFR的参考燃料的早期评估包括在SiC基体中涂覆有SiC的混合碳化物或氮化物微球的陶瓷-陶瓷(陶瓷)分散型复合燃料。研究表明,ZrC具有更高的熔点,更高的抗裂变产物腐蚀能力和更好的化学稳定性,因此可以替代SiC。目前的工作是在ZrC基质中而不是在SiC中研究天然碳化铀微球;传统制造过程中已知的次vol系元素挥发性较小的问题需要研究仍然高温但更快速的制造技术,以最大程度地减少这些预期的损失。在这方面,研究了通过燃烧合成由锆和石墨粉制备的ZrC基体。建立了获得足够的基质密度(UC微球体积分数高达30%)的标准。涉及通过火花腐蚀法生产微球的试验(类似于放电加工)表明,该方法无法生产所需的300至1200微米的UC微球。开发了一种旋转电极装置,使用的最小电流为80A,并以高达1500 rpm的速度旋转,以制造355至1200微米之间的微球。利用ZrC的工艺知识,制造并研究了UC电极,并将其用于旋转电极设备中以生产UC微球。使用10%,20%和30%的微球体积分数研究了cercer复合形式的制备。对复合材料和各个组件在各个阶段的宏观结构进行表征,以了解所需的制造技术,并同时满足必要的GFR燃料特性。

著录项

  • 作者

    Vasudevamurthy, Gokul.;

  • 作者单位

    University of South Carolina.;

  • 授予单位 University of South Carolina.;
  • 学科 Engineering Nuclear.
  • 学位 Ph.D.
  • 年度 2007
  • 页码 200 p.
  • 总页数 200
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类 原子能技术;
  • 关键词

  • 入库时间 2022-08-17 11:39:19

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