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Fluctuations of Mass Yield Distribution for the Epithermal Fission of ~(235)U and Its Impact on HCLWR Calculations

机译:〜(235)U的超热裂变质量产率分布的波动及其对HCLWR计算的影响

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摘要

The need for accurate nuclear data represents a permanent challenge to improve the calculation tools used in reactor physics. Uranium-235 is one of the most important isotopes, and its related nuclear data need to be known with a high degree of accuracy. In this context, many studies have been undertaken to improve the fission yields of ~(235)U for the main fission products in spent fuels. For a few years, an increasing interest has been observed for high-conversion light water reactors, for better use of the fuel and for nonproliferation considerations. These concepts are based on a low moderation ratio (~0.9) and the use of highly enriched mixed oxide fuels (>8%). Because of a neutron flux much harder than in pressurized water reactors, calculations require a good knowledge of nuclear data in the epithermal range to accurately predict the fuel depletion with burnup. In particular, the energy dependence of the fission yields must be considered, because of the existence of fluctuations of the fragment fission yields in the resonances of~(235)U(n,f). Unfortunately, the fluctuations are incorrectly taken into account in calculation codes because of the rough energy description in the usual nuclear data libraries. In this paper, integral experiments are presented for the identification and the quantification of this effect in an almost 1/E neutron spectrum. The experiments consist of the irradiation of ~(235)U samples in the MINERVE reactor (CEA Cadarache), first in a mostly thermal neutron spectrum and second in a mostly epithermal one. Measurements of some abundant fission products are realized with gamma-ray spectrom-etry and show fluctuations of the ~(235)U cumulative fission yields between the two experiments. Results are interpreted with the multimodal random neck rupture model as a variation of 5% of the weight ratio w_1/w_2 between the standard I and standard II fission modes, and compared with the differential experiments.
机译:对精确核数据的需求是改进反应堆物理中使用的计算工具的永久性挑战。铀235是最重要的同位素之一,需要高度准确地知道其相关的核数据。在这种情况下,已经进行了许多研究来提高乏燃料中主要裂变产物的〜(235)U的裂变产率。几年来,人们对高转化率轻水反应堆,燃料的更好利用以及不扩散方面的关注日益增长。这些概念基于低调节比(〜0.9)和使用高浓混合氧化物燃料(> 8%)。由于中子通量比压水堆中的中子通量要难得多,因此计算需要对超热范围内的核数据有充分的了解,才能准确预测燃尽时的燃料消耗。特别地,由于〜(235)U(n,f)的共振中存在碎片裂变产率的波动,因此必须考虑裂变产率的能量依赖性。不幸的是,由于常规核数据库中对能量的粗略描述,在计算代码中没有正确考虑波动。在本文中,提出了积分实验,用于在几乎1 / E中子谱中识别和量化这种效应。实验包括在MINERVE反应堆(CEA卡达拉奇)中辐照〜(235)U样品,首先是在大部分是热中子光谱中,然后是在大部分是超热中子光谱中。用伽马射线能谱仪测量了一些丰富的裂变产物,显示了两次实验之间〜(235)U累积裂变产率的波动。用多峰随机颈裂模型将结果解释为标准I和标准II裂变模式之间重量比w_1 / w_2的5%的变化,并与差异实验进行了比较。

著录项

  • 来源
    《Nuclear science and engineering》 |2012年第2期|p.208-215|共8页
  • 作者单位

    CEA, DEN, DER/SPRC/LEPh Cadarache, F-13108 St. Paul lez Durance;

    CEA, DEN, DER/SPRC/LPN Cadarache, F-13108 St. Paul lez Durance;

    CEA, DEN, DER/SPEX/LPE Cadarache, F-13108 St. Paul lez Durance;

  • 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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