Fission Reactor Engineering Technology ×

Showing 2 of 2 papers in Fission Reactor Engineering Technology

Performance of the CENDL-3.2 and other major neutron data libraries for criticality calculations

Zhang, Bin, Ma, Xu-Bo, Hu, Kui, Zhang, Teng, Ma, Xuan, Chen, Yi-Xue, Ma, Xu-Bo
2021-12-31 ChinaXiv: chinaxiv-202201.00015

Nuclear data are the cornerstones of reactor physics and shielding calculations. Recently, China released CENDL-3.2 in 2020, and the United States released ENDF/B-VIII.0 in 2018. Therefore, it is necessary to comprehensively evaluate the criticality computing performance of these newly released eval…

Application of homogenization techniques for inflow transport approximation on light water reactor analysis

Xiao, Xiang, Wang, Kan, Yang, Tong-Rui, Chen, Yi-Xue, Xiao, Xiang, Wang, Kan
2021-12-31 ChinaXiv: chinaxiv-202201.00014

The transport cross-section based on inflow transport approximation can significantly improve the accuracy of light water reactor (LWR) analysis, especially for the treatment of the anisotropic scattering effect. The previous inflow transport approximation is based on the moderator cross-section and…