Three-dimensional method of characteristics/diamond-difference transport analysis method in STREAM for whole-core neutron transport calculation

2021 ◽  
Vol 260 ◽  
pp. 107332 ◽  
Author(s):  
Sooyoung Choi ◽  
Deokjung Lee
Keyword(s):  
Method Of Characteristics ◽  
Neutron Transport ◽  
Three Dimensional ◽  
Analysis Method ◽  
Transport Calculation ◽  
Transport Analysis

A new three-dimensional method of characteristics for the neutron transport calculation

2011 ◽  
Vol 38 (2-3) ◽  
pp. 447-454 ◽  
Author(s):  
Zhouyu Liu ◽  
Hongchun Wu ◽  
Liangzhi Cao ◽  
Qichang Chen ◽  
Yunzhao Li
Keyword(s):  
Method Of Characteristics ◽  
Neutron Transport ◽  
Three Dimensional ◽  
Transport Calculation

Development of a Two-Dimensional Modularity Characteristics Code for Neutron Transport Calculation

2013 ◽  
Author(s):  
Liang Liang ◽  
Hongchun Wu ◽  
Liangzhi Cao ◽  
Youqi Zheng
Keyword(s):  
Large Scale ◽  
Method Of Characteristics ◽  
Neutron Transport ◽  
Engineering Application ◽  
Polar Angle ◽  
Two Dimensional ◽  
Coarse Mesh ◽  
Characteristics Method ◽  
Large Scale Problems ◽  
Transport Calculation

The method of characteristics (MOC) has been widely used in lattice code for its high precision and easy complement. However, the long characteristics method needs large quantity of PC memory when dealing with large scale problems. The modularity MOC method could significantly reduce the PC memory when calculating the problem which contains lots of repeatedly geometries, like the fuel assembly in the reactor. In this method, only typical geometric cells are selected to trace the rays, and then the geometry information of these cells is stored. So, the modularity MOC method is feasible to perform well in the calculation with large scale. When tracing the rays, the technique of mesh ray generating and the corresponding azimuthal quadrature set are both applied. The techniques make sure that each ray has the reflected ray in the boundary so it is convenient to describe the boundary condition. The optimal polar angle and the Guass quadrature set are selected as the polar quadrature set. Furthermore, the coarse mesh finite difference (CMFD) is employed to accelerate the calculation. A pin cell is chosen as the coarse mesh. The CMFD solution provides the MOC with much faster converged fission and scattering source distributions. The LOTUS code is developed and the numerical results show that the code is precise for engineering application and the CMFD acceleration is effective.

A Three-Dimensional Variational Nodal Method for Pin-Resolved Neutron Transport Analysis of Pressurized Water Reactors

2017 ◽  
Vol 188 (2) ◽  
pp. 160-174 ◽  
Author(s):  
Tengfei Zhang ◽  
Yongping Wang ◽  
E. E. Lewis ◽  
M. A. Smith ◽  
W. S. Yang ◽  
...  
Keyword(s):  
Neutron Transport ◽  
Three Dimensional ◽  
Pressurized Water Reactors ◽  
Pressurized Water ◽  
Nodal Method ◽  
Transport Analysis ◽  
Water Reactors

scholarly journals Preliminary study on CAD-based method of characteristics for neutron transport calculation

2014 ◽  
Vol 38 (5) ◽  
pp. 058201 ◽  
Author(s):  
Zhen-Ping Chen ◽  
Hua-Qing Zheng ◽  
Guang-Yao Sun ◽  
Jing Song ◽  
Li-Juan Hao ◽  
...  
Keyword(s):  
Method Of Characteristics ◽  
Neutron Transport ◽  
Transport Calculation ◽  
Preliminary Study
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