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Nuclear Power Engineering
0258-0926
2009 Issue S1
Numerical Simulation of Flow Behavior in Tight Lattice Rod Bundle
YU Yi-qi1;YANG Yan-hua1;GU Han-yang1;CHENG Xu1 SONG Xiao-ming2;WANG Xiao-jun3
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page:1-5
qian yan
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page:3
Low-Temperature Release Mechanism of Kr and Xe in Fuel Pellet
ZHOU Yi
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page:6-8+13
Angular Discretization of Neutron Transport Equation Based on Daubechies Wavelets
ZHENG You-qi1;WU Hong-chun1;CAO Liang-zhi1;YU Ying-rui2
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page:9-13
Research on and Code Development of Direct Simulation Method for Neutron Space-Time Kinetics
SHEN Hua-yun;WANG Kan
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page:14-17
Application of Wavelets Scaling Function Expansion to Continuous-Energy Neutron Transport Calculation
YANG Wei-yan;WU Hong-chun;CAO Liang-zhi;ZHENG You-qi
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page:18-22+38
Validation of Coupled RELAP5-TDNK Code Using OECD/NEA Core Transient Benchmark
LI Feng;ZHANG Yu;JIANG Guang-ming
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page:23-27
International Research Progress of CFD Application in Analysis of Nuclear Power System
LI Lin-sen1;WANG Kan1;SONG Xiao-ming2
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page:28-33
Research on Application of CFD Method in Thermal-Hydraulic Performance Analysis of Rod Bundle Grid
CHEN Wei-hong;ZHANG Hong;ZHU Li;XIONG Wan-yu
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page:34-38
CFD Research on Flow and Heat Transfer Characteristics of Coolant in Pebble Bed Reactor Core
LI Hua1;QIU Sui-zheng1;SU Guang-hui1;SONG Xiao-ming2
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page:39-43
Application of Nuclear Safety Principle for Reactor Protection System in QinShan Phase II NPP Extension Project
XIAO Peng;XU Dong-fang;FENG Wei
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page:44-47
Research on Engineering Simulator for Function Validating of DCS in Nuclear Power Plant
LIU Peng-fei1;LIN Meng1;HOU Dong1;CHEN Zhi2;YANG Yan-hua1
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page:48-51+64
Automatic Start-up System of Nuclear Reactor Based on Sequence Control Technology
ZHANG Yao1;PENG Hua-qing2;ZHANG Da-fa1
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page:52-55
Research on Flow Distribution in UTSG under Low Flow Rate Condition
ZHANG Yong;SONG Xiao-ming;HUANG Wei
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page:56-59+64
Theoretical Study on Effect of Ocean Conditions on Single-Phase Forced Circulation
DU Si-jia1;ZHANG Hong2
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page:60-64
Numerical Simulation of Flow and Heat Transfer Characteristics Focused on Gas-Liquid Two-Phase Flow Case in Core Simulator of MIPR
NIE Hua-gang;SONG Xiao-ming;NIU Wen-hua
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page:65-69
Study on Generation of Artificial Accelerogram from Shock Response
WU Wan-jun;LIU Wen-jin;ZHANG Yi-xiong
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page:70-71
Virtual Maintenance Technology for Reactor System Based on PPR Technology
WU Ya-xiang;MA Bai-yong
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page:72-76
Study on Categorization of Components Based on Binary Importance Decision
ZENG Wei;YU Hong-xing;SUN Yu-fa
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page:77-81
Application of Computer Aided Tolerance Ananlysis in Product Design
DU Hua
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page:82-85
he dong li gong cheng gao yue
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page:86