On the Response Matrix–Constant Nodal method applied to SN problems with arbitrary L’th-order anisotropic scattering

2021 ◽  
Vol 160 ◽  
pp. 108388
Author(s):  
Jesús P. Curbelo ◽  
Ricardo C. Barros
Keyword(s):  
Anisotropic Scattering ◽  
Response Matrix ◽  
Nodal Method

The Generation of Few-Group Constants for Fast Reactor Analysis

2016 ◽  
Author(s):  
Xianan Du ◽  
Liangzhi Cao ◽  
Youqi Zheng
Keyword(s):  
Monte Carlo ◽  
Cross Section ◽  
Cross Sections ◽  
Fast Reactor ◽  
Monte Carlo Calculation ◽  
Anisotropic Scattering ◽  
Slowing Down ◽  
Nodal Method ◽  
Reactor Calculation ◽  
Broad Energy

A way to generate the few-group cross sections for fast reactor calculation is presented in this paper. It is based on the three steps computational scheme. In the first step, the ultrafine method is used to solve the slowing down equation based on the ultrafine group cross section generated by NJOY. Optional 0D or 1D calculation is used to collapse energy group into broad energy groups. In the second step, the 2D RZ calculation using SN method is performed to obtain the space dependent neutron spectra to collapse broad energy groups into few groups. The anisotropic scattering is well handled by the direct SN calculation. Finally, the full core calculation is performed by using the 3D SN nodal method. The results are compared with continuous energy Monte-Carlo calculation. Both the cross section generated in the first step and the final keff in the last step are compared. The results match well between the three steps calculation and Monte-Carlo calculation.

Exponential Function Expansion Nodal Diffusion Method

2010 ◽  
Author(s):  
Yunzhao Li ◽  
Hongchun Wu ◽  
Liangzhi Cao ◽  
Qichang Chen
Keyword(s):  
Exponential Function ◽  
Flux Distribution ◽  
Diffusion Method ◽  
Response Matrix ◽  
Nodal Method ◽  
Function Expansion ◽  
Diffusion Calculation ◽  
Nodal Diffusion ◽  
Triangular Block ◽  
Neutron Diffusion Equation

An exponential function expansion nodal diffusion method is proposed to take care of diffusion calculation in unstructured geometry. Transverse integral technique is widely used in nodal method in regular geometry, such as rectangular and hexagonal, while improper in arbitrary triangular geometry because of the mathematical singularity. In this paper, nodal response matrix is derived by expanding detailed nodal flux distribution into a sum of exponential functions, and nodal balance equation can be obtained by strict integral in the polygonal node. Numerical results illustrate that the exponential function expansion nodal method in rectangular and triangular block can solve neutron diffusion equation in regular and irregular geometry.

A response matrix spectral nodal method for energy multigroup X,Y-geometry discrete ordinates problems in non-multiplying media

2020 ◽  
Vol 125 ◽  
pp. 103288
Author(s):  
Odair Pinheiro da Silva ◽  
Mateus R. Guida ◽  
Hermes Alves Filho ◽  
Ricardo C. Barros
Keyword(s):  
Discrete Ordinates ◽  
Response Matrix ◽  
Nodal Method
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