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Evaluation of Neutron Cross Sections for a Complete Set of Nd Isotopes

机译:完整Nd同位素的中子截面评估

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Neutron cross sections for a complete set of Nd isotopes, ~(l42,143,144,145,146,147,148,150)Nd, were evaluated in the incident energy range from 10~(-5) eV to 20 MeV. In the low-energy region, including thermal and resolved resonances, our evaluations are based on the latest data published in the Atlas of Neutron Resonances, Fifth Edition: Resonance Parameters and Thermal Cross Sections, Z = 1 - 100. In the unresolved resonance region, we performed additional evaluation by using the averages of the resolved resonances and adjusting them to the experimental data. In the fast neutron region, we used the nuclear reaction model code EMPIRE-2.19 validated against the experimental data. The results are compared to the existing nuclear data libraries, including ENDF/B-VI.8, JENDL-3.3, and JEFF-3.1, and to the available experimental data. The new evaluations are suitable for neutron transport calculations, and they were adopted by the new U.S. evaluated nuclear data ENDF/B-VII.O, released in December 2006.
机译:在入射能范围为10〜(-5)eV至20 MeV的范围内,对整套Nd同位素〜(142,143,144,145,146,147,148,150)Nd的中子截面进行了评估。在低能区域,包括热共振和解析共振,我们的评估基于《中子共振图集》(第五版)的最新数据:共振参数和热截面,Z = 1-100。在未解析共振区域,我们通过使用解析共振的平均值并将其调整为实验数据进行了额外的评估。在快中子区,我们使用了根据实验数据验证的核反应模型代码EMPIRE-2.19。将结果与现有的核数据库(包括ENDF / B-VI.8,JENDL-3.3和JEFF-3.1)进行比较,并与可用的实验数据进行比较。新的评估适用于中子输运计算,并被2006年12月发布的美国新评估的核数据ENDF / B-VII.O所采用。

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