A way to generate the few-group cross sections for fast reactor calculation is presented in this paper. It is based on the three steps computational scheme. In the first step, the ultrafine method is used to solve the slowing down equation based on the ultrafine group cross section generated by NJOY. Optional 0D or 1D calculation is used to collapse energy group into broad energy groups. In the second step, the 2D RZ calculation using SN method is performed to obtain the space dependent neutron spectra to collapse broad energy groups into few groups. The anisotropic scattering is well handled by the direct SN calculation. Finally, the full core calculation is performed by using the 3D SN nodal method. The results are compared with continuous energy Monte-Carlo calculation. Both the cross section generated in the first step and the final keff in the last step are compared. The results match well between the three steps calculation and Monte-Carlo calculation.
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2016 24th International Conference on Nuclear Engineering
June 26–30, 2016
Charlotte, North Carolina, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5001-5
PROCEEDINGS PAPER
The Generation of Few-Group Constants for Fast Reactor Analysis
Xianan Du,
Xianan Du
Xi’an Jiaotong University, Xi’an, China
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Liangzhi Cao,
Liangzhi Cao
Xi’an Jiaotong University, Xi’an, China
Search for other works by this author on:
Youqi Zheng
Youqi Zheng
Xi’an Jiaotong University, Xi’an, China
Search for other works by this author on:
Xianan Du
Xi’an Jiaotong University, Xi’an, China
Liangzhi Cao
Xi’an Jiaotong University, Xi’an, China
Youqi Zheng
Xi’an Jiaotong University, Xi’an, China
Paper No:
ICONE24-60331, V001T02A015; 7 pages
Published Online:
October 25, 2016
Citation
Du, X, Cao, L, & Zheng, Y. "The Generation of Few-Group Constants for Fast Reactor Analysis." Proceedings of the 2016 24th International Conference on Nuclear Engineering. Charlotte, North Carolina, USA. June 26–30, 2016. V001T02A015. ASME. https://doi.org/10.1115/ICONE24-60331
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