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首页> 外文期刊>Nuclear Instruments & Methods in Physics Research >High-fidelity passive neutron multiplicity measurements and simulations of uranium oxide
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High-fidelity passive neutron multiplicity measurements and simulations of uranium oxide

机译:铀氧化物的高保真被动中子多重性测量和模拟

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摘要

When measuring low-self-multiplication uranium samples by passive neutron multiplicity counting, a technique not commonly used on uranium, there should be a decrease in the doubles counts with increasing enrichment. The reason for this decrease is explained as being due to the reduction in ~(238)U mass, which has a large specific spontaneous fission rate in comparison to the other naturally occurring uranium isotopes. However, this is an over simplification of the actual nuclear physics which is occurring in bulk oxide items. The neutron multiplicity production rates are affected by many factors, such as the items self-multiplication, uranium isotopic composition which controls the spontaneous fission to (α,n) neutron production ratio, and the energy distribution of the emitted neutrons which includes induced fission neutrons. This paper presents a high-fidelity analysis of the passive neutron multiplicity distributions for varying enrichments of known uranium oxide standards. This analysis was performed through physical measurements of standards using the Los Alamos Epithermal Neutron Multiplicity Counter (ENMC) and detailed Monte Carlo N Particle Extended (MCNPX) neutron transport simulations supplemented with best available source term data. The MCNPX simulations reproduced the generic trends observed experimentally but absolute agreement is modest, especially for the triples counting. This suggests improvements in basic nuclear data are needed.
机译:当通过被动中子多重计数法(铀中不常用的一种技术)测量低自我增殖铀样品时,随着富集度的增加,双数计数应减少。这种减少的原因被解释为是由于〜(238)U质量的减少,与其他自然存在的铀同位素相比,它具有较大的比自发裂变率。但是,这是对大块氧化物中实际核物理的过度简化。中子多重生产率受到许多因素的影响,例如自扩散项,控制自发裂变与(α,n)中子产生比的铀同位素组成以及包括感应裂变中子在内的发射中子的能量分布。 。本文针对各种已知铀氧化物标准品的富集,对被动中子多重性分布进行了高保真度分析。该分析是通过使用洛斯阿拉莫斯超热中子多重计数器(ENMC)和详细的蒙特卡洛N粒子扩展(MCNPX)中子输运模拟对标准物进行物理测量而进行的,并补充了最佳的可用源项数据。 MCNPX模拟重现了实验观察到的一般趋势,但绝对一致程度不高,尤其是在三元组计数方面。这表明需要改进基本核数据。

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