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.
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2013 21st International Conference on Nuclear Engineering
July 29–August 2, 2013
Chengdu, China
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5582-9
PROCEEDINGS PAPER
Development of a Two-Dimensional Modularity Characteristics Code for Neutron Transport Calculation Available to Purchase
Liang Liang,
Liang Liang
Xi’an Jiaotong University, Xi’an, Shaanxi, China
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Hongchun Wu,
Hongchun Wu
Xi’an Jiaotong University, Xi’an, Shaanxi, China
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Liangzhi Cao,
Liangzhi Cao
Xi’an Jiaotong University, Xi’an, Shaanxi, China
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Youqi Zheng
Youqi Zheng
Xi’an Jiaotong University, Xi’an, Shaanxi, China
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Liang Liang
Xi’an Jiaotong University, Xi’an, Shaanxi, China
Hongchun Wu
Xi’an Jiaotong University, Xi’an, Shaanxi, China
Liangzhi Cao
Xi’an Jiaotong University, Xi’an, Shaanxi, China
Youqi Zheng
Xi’an Jiaotong University, Xi’an, Shaanxi, China
Paper No:
ICONE21-15725, V005T11A008; 9 pages
Published Online:
February 7, 2014
Citation
Liang, L, Wu, H, Cao, L, & Zheng, Y. "Development of a Two-Dimensional Modularity Characteristics Code for Neutron Transport Calculation." Proceedings of the 2013 21st International Conference on Nuclear Engineering. Volume 5: Fuel Cycle, Radioactive Waste Management and Decommissioning; Reactor Physics and Transport Theory; Nuclear Education, Public Acceptance and Related Issues; Instrumentation and Controls; Fusion Engineering. Chengdu, China. July 29–August 2, 2013. V005T11A008. ASME. https://doi.org/10.1115/ICONE21-15725
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