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HFCAS OpenIR

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Investigation on the Tritium Self-Sufficiency and Neutron Shielding Based on a Water-Cooled Blanket for CFETR at 1.5 GW 期刊论文
IEEE TRANSACTIONS ON PLASMA SCIENCE, 2021, 卷号: 49
作者:  Li, Jie;  Zhang, Jie;  Liu, Changle;  Liu, Xiaogang;  Gao, Xiang
收藏  |  浏览/下载：37/0  |  提交时间：2021/11/15
Neutrons  Plasmas  Solid modeling  Inductors  Production  Optimization  Loading  China Fusion Engineering Test Reactor (CFETR)  neutronics study  neutron wall loading (NWL)  tritium breeding ratio (TBR)  water-cooled ceramic breeder (WCCB)  
An upward 9.4 T static magnetic field inhibits DNA synthesis and increases ROS-P53 to suppress lung cancer growth 期刊论文
TRANSLATIONAL ONCOLOGY, 2021
作者:  Yang, Xingxing;  Song, Chao;  Zhang, Lei;  Wang, Junjun;  Yu, Xin;  Yu, Biao;  Zablotskii, Vitalii;  Zhang, Xin
浏览  |  Adobe PDF(4320Kb)  |  收藏  |  浏览/下载：72/30  |  提交时间：2021/12/15
An adaptive regularized iterative FBP algorithm with high sharpness for irradiated fuel assembly reconstruction from few projections in FNCT 期刊论文
ANNALS OF NUCLEAR ENERGY, 2020, 卷号: 145
作者:  Li, Sangang;  Dong, Zhengyun;  Gan, Quan;  Song, Jing;  Yang, Qi
收藏  |  浏览/下载：43/0  |  提交时间：2020/10/26
Fast neutron computed tomography  Irradiated fuel assemblies  Filtered back-projection algorithm  Simultaneous iterative reconstruction technique  Median root prior  Total variation  
Enhanced Erosion-Corrosion Resistance of Tungsten by Carburizing Using Spark Plasma Sintering Technique 期刊论文
MATERIALS, 2020, 卷号: 13
作者:  Jiang, Yan;  Yang, Junfeng;  Xie, Zhuoming;  Fang, Qianfeng
浏览  |  Adobe PDF(5247Kb)  |  收藏  |  浏览/下载：95/41  |  提交时间：2020/10/23
tungsten  W-Cr-C coating  carburization  intergranular corrosion  pitting corrosion  
Operation and shutdown dose rate analysis of CFETR ECRH system 期刊论文
Fusion Engineering and Design, 2020, 卷号: 159
作者:  Peng Lu;  Qiuran Wu;  Liyuan Zhang;  Yu Zheng;  Hua Du;  Kun Xu;  Songlin Liu;  Xiaojie Wang;  Jianjun Huang;  Bin Yu
浏览  |  Adobe PDF(7206Kb)  |  收藏  |  浏览/下载：83/32  |  提交时间：2020/10/23
CFETR, ECRH, Operation dose, Shutdown dose, NASCA  
Development of a wide-range neutron flux monitoring system in EAST 期刊论文
JOURNAL OF INSTRUMENTATION, 2020, 卷号: 15
作者:  Zhong, G. Q.;  Li, K.;  Hu, L. Q.;  Cao, H. R.;  Zhou, R. J.;  Lin, S. Y.;  Hong, B.;  Huo, Z. P.;  Zhang, H.;  Xiao, M.;  Zhou, M. J.;  Zhang, R. X.;  Huang, L. S.;  Huang, J.;  Fan, T. S.;  Zhang, Y. M.
收藏  |  浏览/下载：43/0  |  提交时间：2020/11/26
Nuclear instruments and methods for hot plasma diagnostics  Neutron detectors (cold, thermal, fast neutrons)  Detector alignment and calibration methods (lasers, sources, particle-beams)  Digital electronic circuits  
A MLEM-TV-MRP Algorithm for Fast Neutron Computed Tomography Reconstruction of High Statistical Noise and Sparse Sampling 期刊论文
IEEE ACCESS, 2020, 卷号: 8
作者:  Li, Sangang;  Dong, Zhengyun;  Gan, Quan;  Yu, Shengpeng;  Yang, Qi;  Song, Jing
浏览  |  Adobe PDF(7312Kb)  |  收藏  |  浏览/下载：113/35  |  提交时间：2020/10/22
Fast neutron computed tomography  maximum likelihood-expectation maximization  total variation  median root prior  
Toughening mechanisms of epoxy resin using aminated metal-organic framework as additive 期刊论文
MATERIALS LETTERS, 2019, 卷号: 240, 期号: 无, 页码: 113-116
作者:  Hu, Chen;  Xiao, Juan-Ding;  Mao, Xiao-Dong;  Song, Liang-Liang;  Yang, Xin-Yi;  Liu, Shao-Jun
浏览  |  Adobe PDF(1363Kb)  |  收藏  |  浏览/下载：108/39  |  提交时间：2020/05/21
Shielding material  Epoxy resin  Polymers  Mechanical properties  Porous materials  Metal-organic frameworks  
Stability analysis on flow parameters in coolant temperature control system of lead-cooled fast reactor 期刊论文
ANNALS OF NUCLEAR ENERGY, 2019, 卷号: 126, 期号: 无, 页码: 367-375
作者:  Yao, Yuantao;  Wang, Jianye;  Zhang, Junjun;  Yang, Minghan
浏览  |  Adobe PDF(1997Kb)  |  收藏  |  浏览/下载：126/50  |  提交时间：2020/05/21
Lead-cooled fast reactor  Coolant temperature control system  Coolant flow rate  Stability analysis  Real stability radius  
Insights into potential consequences of fusion hypothetical accident, lessons learnt from the former fission accidents 期刊论文
ENVIRONMENTAL POLLUTION, 2019, 卷号: 245, 期号: 无, 页码: 921-931
作者:  Nie, Baojie;  Ni, Muyi;  Liu, Jinchao;  Zhu, Zhilin;  Zhu, Zuolong;  Li, Fengchen
浏览  |  Adobe PDF(3380Kb)  |  收藏  |  浏览/下载：105/43  |  提交时间：2020/05/21
Fusion reactor  Tritium  Hypothetical accident  Chernobyl  Fukushima