Three Dimension Neutron Transport Characteristics Method Code（Ⅰ）——Interpolation Treatment of Boundary Condition

CHAI Xiaoming; YAO Dong; WANG Kan

Volume 31 Issue 2

Apr. 2010

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CHAI Xiaoming, YAO Dong, WANG Kan. Three Dimension Neutron Transport Characteristics Method Code（Ⅰ）——Interpolation Treatment of Boundary Condition[J]. Nuclear Power Engineering, 2010, 31(2): 11-15.

Citation:

CHAI Xiaoming, YAO Dong, WANG Kan. Three Dimension Neutron Transport Characteristics Method Code（Ⅰ）——Interpolation Treatment of Boundary Condition[J]. Nuclear Power Engineering, 2010, 31(2): 11-15.

Citation:

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Three Dimension Neutron Transport Characteristics Method Code（Ⅰ）——Interpolation Treatment of Boundary Condition

1. Department of Engineering Physics, Tsinghua University, Beijing, 100084, China;
2. National Key Laboratory of Reactor System Design Technology, Nuclear Power Institute of China, Chengdu, 610041, China

Received Date: 2009-01-09
Rev Recd Date: 2009-04-27

Available Online: 2025-07-29

Publish Date: 2010-04-01

Abstract

Abstract

Spatial and angular problems exist when Method of Characteristics（MOC） treats the reflective boundary condition in 3-D neutron transport problems.Spatial interpolation method and angular interpolation method are proposed to solve the spatial problem and the angular problem respectively.There is no restriction on the choice of angular product quadrature set and ray trajectories layout,when using the interpolation method to treat the reflective boundary condition.
- Neutron transport equation,
- Method of Characteristics,
- Reflective boundary condition,
- Interpolation