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

Author:

Liu Zhouyu,Wu Hongchun,Cao Liangzhi,Chen Qichang,Li Yunzhao

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference16 articles.

1. Askew, J.R., 1972. A characteristics formulation of the neutron transport equation in complicated geometries. Report AEEW-R-1108, UK Atomic Energy Authority Establishment, Winfrith.

2. Chai, X., Yao, D., Wang, K., 2009. The linear source approximation in three dimension characteristics method. International Conference on Mathematics, Computational Methods & Reactor Physics (M&C 2009). American Nuclear Society, Saratoga Springs, New York, May 3–7.

3. Auto MOC—a 2D neutron transport code for arbitrary geometry based on the method of characteristics and customization of AutoCAD;Chen;Nucl. Eng. Des.,2008

4. Fundamentals and recent developments of reactor physics methods;Cho;Nucl. Eng. Technol.,2005

5. Cell based CMFD formulation for acceleration of whole-core method of characteristics calculations;Cho;J. Korean Nucl. Soc.,2002

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