Xie Zhongsheng

Study on Composite Material for Shielding Mixed Neutron and $\gamma$-Rays

Huasi Hu, Qunshu Wang, Juan Qin et al. · IEEE Transactions on Nuclear Science · 2008 · 99 citations

Engineering, Materials Engineering, Materials Science +17

A Discrete Ordinates Nodal Method for One-Dimensional Neutron Transport Calculation in Curvilinear Geometries

Yican Wu, Xie Zhongsheng, U. Fischer · Nuclear Science and Engineering · 1999 · 68 citations

Engineering, Computational Engineering, Nuclear Engineering +16

A novel channel selection method for CANDU refuelling based on the BPANN and GA techniques

Xiaodong Huo, Xie Zhongsheng · Annals of Nuclear Energy · 2005 · 20 citations

Management, Supply Chain Management, Channel Management +4

Flux expansion nodal method for solving multigroup neutron diffusion equations in hexagonal-z geometry

Bangyang Xia, Xie Zhongsheng · Annals of Nuclear Energy · 2005 · 20 citations

Engineering, Computational Engineering, Nuclear Engineering +15

MCMG: A 3-D Multigroup P₃ Monte Carlo Code and Its Benchmarks

Deng Li, Xie Zhongsheng, Jianming Zhang · Journal of Nuclear Science and Technology · 2000 · 13 citations

Engineering, Nuclear Engineering, Physics +17