In the other code, the Nodal Green's Function Method was used to solve space-time dependent neutron diffusion equation.
在另一个程序中,用节块格林函数方法解时-空中子动力学方程。
A kinetics nodal method for the solution of transient two-group multi - dimensional neutron diffusion equation is described.
介绍一种求解瞬态两群多维中子扩散方程的动力学节块方法。
First, the neutron diffusion equation is converted to three coupled one dimensional partial flux equation through transverse integration.
首先通过横向积分将中子扩散方程化为三个互相耦合的一维偏通量方程。
A variational formula combining mixed finite element method with discontinuous finite element method is derived for solving the two-group neutron diffusion equation in 2d.
构造了求解二维两群中子扩散方程的混合间断有限元格式,研制了相应的计算程序。
The Green's function in Cartesian geometry can be used to replace the complex Green's function in cylindrical geometry when solving the neutron diffusion equation in cylindrical geometry.
用格林函数节块法求解圆柱几何中子扩散方程时,可用平板几何格林函数代替复杂的圆柱几何格林函数。
An diffusion Synthetic acceleration equation and differencing scheme (DSA) for the diamond scheme of the one-dimensional sphere geometry steady neutron transport equation is introduced in this report.
本文导出了一维球几何定态中子输运方程菱形格式的扩散综合加速方程,并给出了差分公式。
To calculate the neutron distribution, in this case, a rather big errors would occur if the diffusion theory be used. However, Monte Carlo Method is suitable at dealing with the problem.
在这种情况下,如果采用扩散理论计算这种组件内的中子分布,会引起相当大的误差,但蒙特卡罗方法是非常适合于处理这种情况的。
It is found that the neutron skin and the neutron distribution diffusion can explam the influence of the neutron excess degree of freedom on the proximity scaling.
详细研究了亲近势标度,发现用中子皮及中子分布弥散度的变化能较好地解释中子过剩自由度对亲近势标度偏离的影响。
It is found that the neutron skin and the neutron distribution diffusion can explam the influence of the neutron excess degree of freedom on the proximity scaling.
详细研究了亲近势标度,发现用中子皮及中子分布弥散度的变化能较好地解释中子过剩自由度对亲近势标度偏离的影响。
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