Method for calculating anisotropic neutron transport using scattering kernel without polynomial expansion.
Method for calculating anisotropic neutron transport using scattering kernel without polynomial expansion.
复制标题
使用无需多项式展开的散射核计算各向异性中子输运的方法。
DOI：
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发表时间：
1979
期刊：
影响因子：
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通讯作者：
K. Sumita
中科院分区：
文献类型：
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作者：
A. Takahashi;J. Yamamoto;Mituo Ebisuya;K. Sumita
本文提出了一种计算各向异性中子输运的新方法，用于D-T聚变堆中子学的角谱分析。该方法基于输运方程，其新型各向异性散射核由单个函数Ii（μ′，μ）代替多项式展开（如Legendre多项式）表示.在用勒让德多项式展开的散射核计算角通量谱时，经常会观察到负通量的振荡现象。但原则上，通过这种新方法，这种振荡消失了。本文讨论了激发离散能级的弹性散射和非弹性散射的各向异性散射核。其他散射被包含在各向同性散射核中。当我们必须使用勒让德多项式的散射核时，引入了一种近似方法，用Ii（μ′，μ）函数表示第一碰撞源，以减弱“振荡”。
A new method for calculating the anisotropic neutron transport is proposed for the angular spectral analysis of D-T fusion reactor neutronics. The method is based on the transport equation with new type of anisotropic scattering kernels formulated by a single function Ii (μ′,μ) instead of polynomial expansion, for instance, Legendre polynomials. In the calculation of angular flux spectra by using scattering kernels with the Legendre polynomial expansion, we often observe the oscillation with negative flux. But in principle this oscillation disappears by this new method. In this work, we discussed anisotropic scattering kernels of the elastic scattering and the inelastic scatterings which excite discrete energy levels. The other scatterings were included in isotropic scattering kernels. An approximation method, with use of the first collision source written by the Ii (μ′,μ) function, was introduced to attenuate the “oscillations” when we are obliged to use the scattering kernels with the Legendre polynomia...