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Chinese Journal of Nuclear Science and Engineering
0258-0918
2009 Issue 1
QMU certifying method and its implementation
MA Zhi-bo;YING Yang-jun;ZHU Jian-shi
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page:1-9
Generation of nodal equivalent homogenized parameters under nonreflective boundary condition for coarse mesh nodal methods
HUANG Hao;TANG Chun-tao
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page:10-15,21
Neutronics/thermal-hydraulics coupled axial 1D model for SCWR core static analysis
LIU Zhan-quan;JIANG Zhu-min;JIANG Xiao-feng;WANG Tao;ZHANG Shao-hong
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page:16-21
Study on judgment arithmetic for the symmetric attribute of plutonium material in sealed container
HU Guang-chun;LIU Su-ping;HAO Fan-hua;XIANG Yong-chun
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page:22-26
Simulation principle and analysis for heat transfer of argon space in the main vessel of China Experimental Fast Reactor
WU Qiang;ZHANG Dong-hui;LIU Yun-yan
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page:27-32
Analysis of sodium/argon flow in anti-siphon equipment's curved pipeline of China Experimental Fast Reactor
PENG Yan;ZHANG Dong-hui
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page:33-38
FaultTree analysis algorithm for Living PSA
HU Wen-jun;YU Hong;REN Li-xia;QIAN Hong-tao;SONG Wei;QIAO Xue-dong
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page:39-42
The design analysis for a mixed neutron spectrum supercritical water-cooled reactor core
CHENG Xu;LIU Xiao-jing
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page:43-49
Effect of yttrium on mechanical properties of 9Cr-2WVTa low active martensite steel
YAN Wei
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page:50-55
Study on the layout of the SCWR fuel assembly
QIN Dong;CHANG Hua-jian
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page:56-61
The thermal hydraulic characteristics of the air heat exchanger in China Experimental Fast Reactor
LI Jing
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page:62-66,85
Numerical testing of HENDL2.1/CG data library with evaluated critical benchmark experiments
HE Zhao-zhong;XU De-zheng;ZOU Jun;CHEN Ming-liang;ZENG Qin;FDS Team
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page:67-70
Integral numerical test of the hybrid evaluated nuclear data library HENDL2.0 for heavy nuclides
XU De-zheng;JIANG Jie-qiong;ZOU Jun;HE Zhao-zhong;CHEN Ming-liang;ZHENG Shan-liang;ZENG Qin;FDS Team
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page:71-75
Magnetohydrodynamic experimental design and analysis for Chinese liquid metal LiPb experimental loop DRAGON-Ⅳ
LU Ruo-jun;CHEN Hong-li;ZHOU Tao;YANG Zhi-yi;FDS Team
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page:76-80
Pilot study on risk informed categorization of structures, systems and components for nuclear power plant
QIAN Yong-bai;ZHAO Jun;TONG Jie-juan;ZHANG Zuo-yi
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page:81-85
A study on calculating the reliability of standby system by fault tree method
SONG Wei;YANG Hong-yi;MIN Yuan-sheng
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page:86-91
Study of the sulfuric acid leaching and bacterial leaching of low grade uranium ore by orbital shaker experiment
LI Guang-yue;LIU Yu-long;WANG Yong-dong;DING De-xin
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page:92-96