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Neutron Multigroup Constant Sets of Moderator Materials for Design of Low-Energy Neutron Sources

机译:用于低能中子源设计的中子多组慢化剂材料常数集

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For design assessment of low-energy neutron sources, neutron multigroup constant sets (energy-averaged cross sections) are developed, which consist of 36 sets of multigroup constants for liquid ~4He, H_2, D_2, CH_4, H_2O and D_2O and solid CH_4 at many different temperatures. The neutron energy range between 0.1 μeV and 10 MeV are divided into 140 energy groups at equal logarithmic intervals. The angular distribution of scattered neutrons is represented by the expansion in Legendre polynomials up to order 3. The multigroup constants at energies below 10 eV are generated using physical models of a double-differential scattering cross section for the moderator materials, which are newly developed for describing low-energy neutron scattering in terms of the general considerations of molecular dynamics and structures inherent in liquid and solid phases.
机译:为了对低能中子源进行设计评估,开发了中子多组常数集(能量平均横截面),其中包括36个液体〜4He,H_2,D_2,CH_4,H_2O和D_2O和固体CH_4的多组常数。许多不同的温度。在0.1μeV和10 MeV之间的中子能量范围以相等的对数间隔分为140个能量组。零散中子的角分布由勒让德多项式的阶数扩展到3表示。能量低于10 eV的多组常数是使用慢化剂材料的双微分散射截面的物理模型生成的,该模型为用分子动力学和液相和固相固有结构的一般考虑来描述低能中子散射。

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