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Reduction of the radiotoxicity of spent nuclear fuel using a two-tiered system comprised of light water reactors and accelerator-driven systems (Nevada).

机译:使用由轻水反应堆和加速器驱动系统组成的两级系统降低乏核燃料的放射毒性(内华达州)。

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摘要

Two main issues regarding the disposal of spent nuclear fuel from nuclear reactors in the United States in the geological repository Yucca Mountain are: (1) Yucca Mountain is not designed to hold the amount of fuel that has been and is proposed to be generated in the next few decades, and (2) the radiotoxicity (i.e., biological hazard) of the waste (particularly the actinides) does not decrease below that of natural uranium ore for hundreds of thousands of years. One solution to these problems may be to use transmutation to convert the nuclides in spent nuclear fuel to ones with shorter half-lives. Both reactor and accelerator-based systems have been examined in the past for transmutation; there are advantages and disadvantages associated with each. By using existing Light Water Reactors (LWRs) to burn a majority of the plutonium in spent nuclear fuel and Accelerator-Driven Systems (ADSs) to transmute the remainder of the actinides, the benefits of each type of system can be realized. The transmutation process then becomes more efficient and less expensive. This research searched for the best combination of LWRs with multiple recycling of plutonium and ADSs to transmute spent nuclear fuel from past and projected nuclear activities (assuming little growth of nuclear energy). The neutronic design of each system is examined in detail although thermal hydraulic performance would have to be considered before a final system is designed. The results are obtained using the Monte Carlo burnup code Monteburns, which has been successfully benchmarked for MOX fuel irradiation and compared to other codes for ADS calculations. The best combination of systems found in this research includes 41 LWRs burning mixed oxide fuel with two recycles of plutonium (∼40 years operation each) and 53 ADSs to transmute the remainder of the actinides from spent nuclear fuel over the course of 60 years of operation.
机译:关于在美国尤卡山地质仓库中处置来自核反应堆的乏核燃料的两个主要问题是:(1)尤卡山的设计目的不是容纳已经和拟在该地区产生的燃料量。在接下来的几十年中,以及(2)数十万年来废物(特别是the系元素)的放射毒性(即生物危害)不会降低到低于天然铀矿石的放射毒性。解决这些问题的一种方法可能是使用trans变将乏核燃料中的核素转化为半衰期较短的核素。过去已经检查了反应堆和基于加速器的系统的trans变。每种都有优点和缺点。通过使用现有的轻水反应堆(LWR)燃烧乏核燃料中的大部分the,并使用加速器驱动系统(ADS)转化其余的act系元素,可以实现每种系统的优势。这样,process变过程将变得更加高效和廉价。这项研究寻求将轻水堆与with和ADS的多次回收以转化过去和预期的核活动(假定核能几乎没有增长)转化为乏核燃料的最佳组合。尽管在设计最终系统之前必须考虑热液压性能,但会详细检查每个系统的中子设计。使用蒙特卡罗燃耗代码 Monteburns 获得了结果,该代码已成功地作为MOX燃料辐照的基准,并与其他代码进行了ADS计算。在这项研究中发现的系统的最佳组合包括:41个轻水堆燃烧混合氧化物燃料,并进行两次(循环(每次运行约40年)和53个ADS,以在60年的运行过程中从乏核燃料中转化剩余的act系元素。 。

著录项

  • 作者

    Trellue, Holly Renee.;

  • 作者单位

    The University of New Mexico.;

  • 授予单位 The University of New Mexico.;
  • 学科 Engineering Nuclear.
  • 学位 Ph.D.
  • 年度 2003
  • 页码 201 p.
  • 总页数 201
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类 原子能技术;
  • 关键词

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