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Fuel geometry options for a moderated low-enriched uranium kilowatt-class space nuclear reactor

机译:缓和的低浓铀千瓦级空间核反应堆的燃料几何选择

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摘要

A LEU-fueled space reactor would avoid the security concerns inherent with Highly Enriched Uranium (HEU) fuel and could be attractive to signatory countries of the Non-Proliferation Treaty (NPT) or commercial interests. The HEU-fueled Kilowatt Reactor Using Stirling Technology (KRUSTY) serves as a basis for a similar reactor fueled with LEU fuel. Based on MCNP6 (TM) neutronics performance estimates, the size of a 5 kW(e) reactor fueled with 19.75 wt% enriched uranium-10 wt% molybdenum alloy fuel is adjusted to match the excess reactivity of KRUSTY. Then, zirconium hydride moderator is added to the core in four different configurations (a homogeneous fuel/moderator mixture and spherical, disc, and helical fuel geometries) to reduce the mass of uranium required to produce the same excess reactivity, decreasing the size of the reactor. The lowest mass reactor with a given moderator represents a balance between the reflector thickness and core diameter needed to maintain the multiplication factor equal to 1.035, with a H/D ratio of 1.81. All three heterogeneous geometries yield a minimum mass reactor using a moderator/fuel ratio of 80 wt%. The lifetime is directly proportional to the initial amount of fissile material in the core in all the cases. Based on the small differences in estimated masses, but large difference in estimated lifetimes between the 60 wt% and 80 wt% moderated reactors, the 60 wt% moderated systems with disc or helical fuel geometries represent the best balance between total mass and operating lifetime.
机译:以低浓铀为燃料的空间反应堆将避免高浓铀(HEU)燃料固有的安全问题,并且对不扩散条约(NPT)的签署国或商业利益具有吸引力。使用斯特林技术(KRUSTY)的HEU燃料的千瓦反应堆(KRUSTY)作为以LEU燃料为燃料的类似反应堆的基础。基于MCNP6(TM)中子学性能估计,对以19.75 wt%浓缩铀-10 wt%钼合金燃料为燃料的5 kW(e)反应堆的大小进行了调整,以匹配KRUSTY的过量反应性。然后,将氢化锆减速剂以四种不同的配置(均质燃料/减速剂混合物以及球形,圆盘形和螺旋形燃料几何形状)添加到堆芯中,以减少产生相同过量反应性所需的铀质量,从而减小铀的大小。反应堆。具有给定调节剂的最低质量反应堆表示反射器厚度与保持倍增系数等于1.035所需的纤芯直径之间的平衡,H / D比为1.81。所有这三种异质几何结构均使用80%(重量)的慢化剂/燃料比产生了最小质量的反应堆。在所有情况下,寿命与芯中易裂变材料的初始量成正比。基于60 wt%和80 wt%的缓和反应堆之间的估计质量差异很小,但估计寿命存在较大差异,具有盘形或螺旋形燃料几何形状的60 wt%缓和系统代表了总质量和使用寿命之间的最佳平衡。

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  • 来源
    《Nuclear Engineering and Design》 |2018年第12期|122-132|共11页
  • 作者单位

    CSM, Nucl Sci & Engn Program, 1500 Illinois St,Hill Hall, Golden, CO 80401 USA;

    CSM, Nucl Sci & Engn Program, 1500 Illinois St,Hill Hall, Golden, CO 80401 USA;

  • 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
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