Calculation of neutron cross sections and thermalization parameters for molecular gases using a synthetic scattering function. II. Applications to H2O, D2O, and C6H6.
Calculation of neutron cross sections and thermalization parameters for molecular gases using a synthetic scattering function. II. Applications to H2O, D2O, and C6H6.
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使用合成散射函数计算分子气体的中子截面和热化参数。
DOI：
10.1103/physreva.36.5594
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发表时间：
1987
期刊：
影响因子：
--
通讯作者：
Mayer
中科院分区：
文献类型：
--
作者：
Granada;Gillette;Mayer
从前文所给出的合成模型推导出的公式被用于计算常用的慢化剂${\mathm{H}}_{2}$O、${\mathm{D}}_{2}$O和${\mathm{C}}_{6}$${\mathrm{H}}_{6}$的热中子能量下的部分截面和总截面。将我们得到的散射核的解析表达式${\ensureath{\sigma}}_{0}$(${E}_{0}$，E)和${\susureath{\sigma}}_{1}$(${E}_{0}$，E)与标准程序计算的入射中子能量${E}_{0}$进行了比较。相应的积分量、总截面和散射角的平均余弦分别与实验数据和其他理论结果进行了比较。在中子扩散理论的框架内，输运系数很容易用模型表达式来估计，并在广泛的温度范围内与现有的信息进行比较。
The formulas derived from the synthetic model which were presented in the preceding paper are here applied to the evaluation of partial and total cross sections at thermal neutron energies for the commonly used moderators ${\mathrm{H}}_{2}$O, ${\mathrm{D}}_{2}$O, and ${\mathrm{C}}_{6}$${\mathrm{H}}_{6}$. The results of our analytical expressions for the scattering kernels ${\ensuremath{\sigma}}_{0}$(${E}_{0}$,E) and ${\ensuremath{\sigma}}_{1}$(${E}_{0}$,E) are compared with standard code calculations for well-separated incident neutron energies ${E}_{0}$. The related integral quantities, total cross section \ensuremath{\sigma}(${E}_{0}$), and average cosine of the scattering angle 〈cos\ensuremath{\theta}(${E}_{0}$)〉, respectively, are also compared with experimental data and results from other theories. Within the framework of neutron diffusion theory, transport coefficients are readily evaluated using the model expressions and they are compared with available information over a wide range of temperatures.