Full Multi-grid Diffusion Synthetic Accelerated Discrete-Ordinates Neutron Transport Numerical Computation Code SN3C

LIU Yong-kang; HU Yong-ming; LIU Han-gang; QIAN Da-zhi

Oct. 2006

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Article Navigation > Nuclear Power Engineering > 2006 > 27(5): 1-5,11

LIU Yong-kang, HU Yong-ming, LIU Han-gang, QIAN Da-zhi. Full Multi-grid Diffusion Synthetic Accelerated Discrete-Ordinates Neutron Transport Numerical Computation Code SN3C[J]. Nuclear Power Engineering, 2006, 27(5): 1-5,11.

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Full Multi-grid Diffusion Synthetic Accelerated Discrete-Ordinates Neutron Transport Numerical Computation Code SN3C

1. Institute of Nuclear and New Energy Technology, Tsinghua University, Beijing, 100084, China;
2. Institute of Nuclear Physics and Chemistry, China Academy of Engineering Physics, Mianyang, Sichuan, 621900, China

Received Date: 2005-07-05
Rev Recd Date: 2006-01-12

Available Online: 2025-07-29

Abstract

Abstract

To improve the performance of the recently developed three-dimensional neutron transport code SN3C,the consistent Diffusion Synthetic Acceleration（DSA） method and the self-adapting Chebyshev polynomial acceleration method were adopted to accelerate the source iteration and power iteration,respectively.According to the characteristics of the method used by the DSA for solving the diffusion equa-tion,the author had developed the Full Multi-grid Diffusion Synthetic Method（FMDSA）,which based on the Full Multi-grid Algorithm.The results of benchmark calculation showed a good agreement with reference value.The performance of FMDSA was demonstrated as good as the block-SOR with optimal relaxation fac-tor for little and medium problems,and moreover,for a large-scale problem,it was better than the latter.
- Discrete-ordinates method,
- Diffusion synthetic method,
- Full multi-grid method,
- Neutron transport equation,
- Numerical computation