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MINOR ACTINIDE TRANSMUTATION IN GFR600

机译:GFR600中的微量氰化物转化

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Within the Generation IV initiative, the gas-cooled fast reactor (GFR) is one of the reactors dedicated to minor actinide (MA) transmutation. This paper summarizes the research performed with the GFR600 reference design in order to assess its MA burning capabilities. For the study, modules of the SCALE program system were used. Single-cycle parametric studies were performed with cores having different MA content and spatial distribution. It was shown that the addition of MAs to the fuel greatly reduced the reactivity loss during burnup. Moreover, the higher the MA content of the core, the higher the fraction of it that was fissioned; however, the more the delayed neutron fraction and the fuel temperature coefficient degraded. Significant reduction can be achieved in the amounts of neptunium and americium, while curium isotopes accumulate. The study of multiple consecutive cycles showed that by adding only depleted uranium (DU) to the reprocessed actinides in fuel fabrication (pure DU feed strategy), up to 70% of the initially loaded MAs can be fissioned in the first five cycles. Moreover, the reactor can be made critical during that time if the initial MA content is higher than 3%. By feeding MAs as well (constant MA content strategy), the reactivity has a steady increase from cycle to cycle, predominantly due to ~(238)Pu breeding from ~(237)Np. The effects of the isotopic composition of the pluto-nium and MAs were also examined by performing calculations with data specific to the spent fuel of traditional western pressure water reactors and Russian type VVER440 reactors. Despite the considerably different MA vectors, no significant deviation was found in their overall transmutation. However, the Pu composition had a strong effect on the reactivity and the delayed neutron fraction in the first cycles. Finally, cores having nonuniform MA content were investigated. It was found that though the MA destruction efficiency was significantly higher in the middle of the core than at the edge, moving some of the MAs from the outer regions to the center resulted in only minor improvement in their destruction. However, the spectral changes caused by the rearrangement increased the k-effective, which allowed higher burnups and increased MA destruction. Unfortunately, some of the safety parameters of the reactor degraded.
机译:在第四代倡议中,气冷快堆(GFR)是专门用于次act系元素(MA)trans变的反应堆之一。本文总结了使用GFR600参考设计进行的研究,以评估其MA刻录功能。为了进行研究,使用了SCALE程序系统的模块。使用具有不同MA含量和空间分布的岩心进行了单周期参数研究。结果表明,向燃料中添加MAs可以大大减少燃尽期间的反应性损失。此外,岩心的MA含量越高,裂变的比例越高;但是,延迟的中子分数和燃料温度系数下降的幅度更大。在cur同位素积累的同时,of和a的含量可以大大降低。对多个连续循环的研究表明,通过在燃料制造中将仅贫化铀(DU)添加到后处理的act系元素中(纯DU进料策略),在最初的五个循环中最多可裂化70%的初始装载MA。此外,如果初始MA含量高于3%,则在此期间可以使反应器变得至关重要。同样通过饲喂MAs(恒定的MA含量策略),反应性逐周期稳定增加,这主要是由于〜(238)Pu从〜(237)Np繁殖而来。 with和MA的同位素组成的影响也通过使用特定于传统西方压力水反应堆和俄罗斯VVER440型反应堆乏燃料的数据进行计算来检查。尽管MA载体有很大不同,但在它们的整体trans变中没有发现明显的偏差。但是,Pu组成在第一个循环中对反应性和延迟的中子分数有很强的影响。最后,研究了具有不均匀MA含量的岩心。已经发现,尽管MA的破坏效率在核心的中部比边缘的边缘要高得多,但是将某些MA从外部区域移动到中心只会导致破坏程度的微小改善。然而,由重排引起的光谱变化增加了k-有效值,这允许更高的燃耗和增加的MA破坏。不幸的是,反应堆的一些安全参数降低了。

著录项

  • 来源
    《Nuclear Technology》 |2012年第1期|p.83-97|共15页
  • 作者单位

    Delft University of Technology, Department of Radiation, Radionuclides and Reactors Mekelweg 15, Delft, Netherlands;

    Delft University of Technology, Department of Radiation, Radionuclides and Reactors Mekelweg 15, Delft, Netherlands;

    Budapest University of Technology, Institute of Nuclear Techniques Muegyetem rakpart 3, Budapest, Hungary;

  • 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

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