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Journals   A B C D E F G H I J K L M N O P Q R S T U V W X Y Z
Nuclear Power Engineering
0258-0926
2006 Issue 4
Hydrodynamic Model of Slug Flow in Vertical Pipes Considering Variable Thickness of Liquid Film
WANG Wei-yang;CHEN Ting-Kuan;LUO Yu-shan;GAO Feng
..............page:97-100
Design of Data Acquisition System in Nuclear Power Station
XU Hui;HUANG Wen-jun;JIANG Zhu-xuan;SU Guo-quan
..............page:93-96
Deposition of Draphite Dust in Heat Gas Duct in HTR-10
LUO Xiao-wei;YU Su-yuan;TANG Hui
..............page:90-92,96
Procurement and Quality Control of Components Important to Safety in Nuclear Engineering Projects
ZHANG Zhi-hua;ZHANG Yi-yun;XU Xian-qi;QIAN Da-zhi;DENG Yue
..............page:86-89
Establishment of Professional Nuclear Power Architectural Engineering Company
GUO Dong-li;CHEN Hua
..............page:83-85
Computer Simulation for Sodium-Concrete Reactions
ZHANG Bin;ZHU Ji-zhou
..............page:75-82,89
On Cyclic Deformation of 304 Stainless Steel under Strain-Controlled Nonproportionally Multiaxial Loading at High Temperatures
ZHANG Juan;GAO Qing;KANG Guo-zheng;LIU Yu-jie
..............page:44-49
Effect of Temperature on Iodine-Induced Stress Corrosion Cracking of Zr-Sn-Nb Alloy
PENG Qian;ZHAO Wen-jin;LI Wei-jun;TANG Zheng-hua;CUI Xu-mei;HENG Xue-mei
..............page:40-43
New Finite Element Method to Analyze Crack Tip of Plate Structure
ZHANG Ji-ping;CHEN Qiu
..............page:35-39
Structure Analysis and Sealing Design of Reactor Building for China Advanced Research Reactor
LI Zhong-xian;RONG Feng;DONG Zhan-fa;FU Ji-yang
..............page:30-34,43
Processing of CHF Experimental Data Base
SHAN Jian-qiang;D.C.Groeneveld;S.C.Cheng
..............page:26-29,39
Analysis on Radiation Heat Transfer between Pressure Tube and Calandria Tube of TACR
XU Liang-wang;JIA Bao-shan
..............page:21-25
Analysis of Forced-Convection Flow Instability in Steam Generator
WU Ge-ping;QIU Sui-zheng;SU Guang-hui;JIA Dou-nan
..............page:16-20,25
Feasibility Study for Monte Carlo Method and Its Application on HFETR γ-Heat Calculation
QIU Li-qing;JIA Dou-nan;DENG Cai-yu;FU Rong;HU Yue-chun;WANG Zhen-dong
..............page:13-15
Fuel Assembly Few Group Parameter Calculation Code AFGPB and Benchmarking
YAO Dong;LI Da-tu;YU Ying-rui;MA Yong-qiang;YIN Qiang
..............page:8-12
Fuel Array Project for the Sub-critical Reactor of Accelerator Driven System Verification Facility
YU Tao;SHI Yong-qian;XIA Pu;LIAO Yi-xiang;XIAN Wen-ping;DU Hai-dong
..............page:5-7
In-Core Fuel Management Design for CNP1500
LI Dong-sheng
..............page:1-4
Study on Virtual Simulation Technology for Operation and Control of PWR
Fang Bao-guo;Zhang Da-fa;Lin Ya-jun
..............page:71-74
Design of Secondary Cooling Water System for China Advanced Research Reactor
RONG Feng;WANG Jian-yong
..............page:68-70,74
Status of Boiler Effect for Safety-Related Gate Valves and Its Improvement
WANG An;XIANG Wen-yuan;LI Shu-zhou
..............page:64-67
Theoretical Design of an Epithermal Neutron Radiation Field
ZHANG Xiao-min;ZHANG Wen-zhong;LUO Yi-sheng
..............page:59-63
Quantification Method of Cognitive Error and Its Application in PSA
WANG Yao;HE Xu-hong;SHEN Zu-pei;HUANG Xiang-rui
..............page:54-58
A Mechanism Investigation of Core Melting in Nuclear Reactor Using Molecular Dynamics Method
CHEN Shuo;SHANG Zhi;ZHAO Jun
..............page:50-53
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