Hui Guo

发表

Influence of nuclear data library on Neutronics Benchmark of China experimental fast reactor start-up tests

H. Gu, Haicheng Wu, Xingkai Huo, 2022, Nuclear Engineering and Technology.

Verification of neutron-induced fission product yields evaluated by a tensor decompsition model in transport-burnup simulations

Long Zhu, Hui Guo, Qufei Song, 2023, Nuclear Science and Techniques.

Design of a shielding collimator device for a small-angle monoenergetic neutron source

K. Zhao, Yijie Hou, Hui Guo, 2018, Nuclear Science and Techniques.

Preliminary verification of multi-group cross-sections generation and locally heterogeneous transport calculation using OpenMC with CEFR start-up tests benchmark

H. Gu, Yiwei Wu, Xingkai Huo, 2022, Progress in Nuclear Energy.

Freeze concentration of proteins in Antarctic krill wash water

Kuo Zhao, Xiangming Qi, Hui Guo, 2017, Journal of Ocean University of China.

Design of a shielding collimator device for a small-angle monoenergetic neutron source

K. Zhao, Yijie Hou, Hui Guo, 2018, Nuclear Science and Techniques.

The design of “multiple energies from one source” in D-T neutron tube

K. Zhao, Hui Guo, Zhi-Hao Wei, 2016 .

Multigroup cross-sections generated using Monte-Carlo method with flux-moment homogenization technique for fast reactor analysis

H. Gu, Yiwei Wu, Hui Guo, 2023, Nuclear Engineering and Technology.

Development and verification of a Monte Carlo two-step method for lead-based fast reactor neutronics analysis

H. Gu, Yao Xiao, Ruixiang Wang, 2023, Nuclear Engineering and Technology.

Development of OpenMC/Trivac two-step scheme for fast reactor core neutronics analysis

H. Gu, Tenglong Cong, Yiwei Wu, 2023, Annals of Nuclear Energy.

Neutronics Modelling of Control Rod Compensation Operation in Small Modular Fast Reactor using OpenMC

Hui Guo, Xingjie Peng, Yiwei Wu, 2021, Nuclear Engineering and Technology.

The role of nuclear energy in the carbon neutrality goal

H. Gu, Tenglong Cong, Maolong Liu, 2023, Progress in Nuclear Energy.