Neutronic Analysis on Potential Accident Tolerant Fuel-Cladding Combination U3Si2-FeCrAl

by Shengli Chen, Cenxi Yuan
Published 2017-01-01

A Simple Formula for Local Burnup and Isotope Distributions Based on Approximately Constant Relative Reaction Rate

by Cenxi Yuan, Xuming Wang, Shengli Chen
Published 2016-01-01

Two-neutron “halo” from the low-energy limit of neutron–neutron interaction: Applications to drip-line nuclei 22C and 24O

by Toshio Suzuki, Takaharu Otsuka, Cenxi Yuan, Navin Alahari
Published 2016-02-01

Core design and neutronic study on small reactor with advanced fuel designs

by Zhaozhan Zhang, Tianfan Wu, Yujing Wang, Shengli Chen, Cenxi Yuan, Jianyu Zhu
Published 2021-12-01

Neutronic Design for Heat Pipe Reactor With Annular and Accident Tolerant Fuels

by Boshuai Cai, Shengli Chen, Tianfan Wu, Yujing Wang, Zhaozhan Zhang, Cenxi Yuan, Chunyu Zhang, Yulin Ge
Published 2021-06-01

Three-Dimensional Modeling of Thermal-Mechanical Behavior of Accident Tolerant Fuels

by Zitao Zeng, Yongyu Pan, Xi Chen, Chunyu Zhang, Chunyu Yin, Shixin Gao, Yi Zhou, Jie Zhang, Xiujie He, Cenxi Yuan
Published 2021-03-01

Isomerism in the “south-east” of 132Sn and a predicted neutron-decaying isomer in 129Pd

by Cenxi Yuan, Zhong Liu, Furong Xu, P.M. Walker, Zs. Podolyák, C. Xu, Z.Z. Ren, B. Ding, M.L. Liu, X.Y. Liu, H.S. Xu, Y.H. Zhang, X.H. Zhou, W. Zuo
Published 2016-11-01