Home | Survey | Payment| Talks & Presentations | Job Opportunities
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
Chinese Journal of Nuclear Science and Engineering
0258-0918
2002 Issue 3
Project Management for Dome Lifting in One Piece for Reactor Building
yang zi chun
..............page:284-288,283
A Variational Solution of Transport Equation Based on Spherical Geometry
liu hui ; zhang ben ai
..............page:274-277
An Experiment Study of the Transient Drag Property on the High-Temperature Particle Falling into the Cold Liquid Pool
li xiao yan ; yang yan hua ; xu ji zuo ; chen hong
..............page:268-273
Study of Transmutation in Modular Fast Reactor Using MOX Fuel
zhou pei de
..............page:261-267
Study on Advanced Nuclear Fuel Cycle of PWR/CANDU Synergism
xie zhong sheng ; huo xiao dong
..............page:256-260,277
Preliminary Study on High Temperature Gas-Cooled Reactor-Combined Cycle Power
chen yi hua ; wang jie ; zhang zuo yi
..............page:250-255
Measurements of Local Liquid Velocity and Interfacial Parameters of Air-Water Bubbly Flows in a Horizontal Tube
yang jian ; zhang ming yuan ; zhang chao jie ; su yu liang ; ren chang chun
..............page:244-249
Three Dimensional Numerical Simulation of Flow in the Shell-Tube Heat Exchanger
jie heng ; gao zu zuo
..............page:240-243,249
Experimental Investigation on Single-phase Convection Heat Transfer in Narrow Annulus
sun li cheng ; yan chang zuo ; sun zhong ning
..............page:235-239
Numerical Calculation of Single Phase Convective Heat Transfer in Narrow Annular Channel
liu rui lan ; wang zeng hui ; gou jun li ; jia dou nan
..............page:229-234,239
Research on Export System of Marine Nuclear Power Device
fu ming yu ; bian xin qian ; shi zuo ; xin cheng dong ; wei dong
..............page:220-228
An Investigation on Steam-Water Two-Phase Forced Convection Boiling Heat Transfer in Helical-Coiled Tubes
zhou yun long ; sun bin ; chen ting kuan ; chen xue jun
..............page:217-219,228
MJTR Core Loading Pattern Optimization Using Genetic Algorithms
peng feng ; peng gang ; fu rong
..............page:212-216
Study of Coolant Steam Quality Calculation in the Heat Channel of Reactors
cai zhang sheng ; zhou gang ; chen zuo xiang
..............page:210-211
The Analysis of Residual Heat Long Time Cooling about Pool-type Reactor
wang yan ; shi zuo ; chen xiao ming ; li jin cai ; zhou zhi wei
..............page:204-209
Analysis of Natural Circulation Ability in PWR Coolant System under Ocean Condition
yang zuo ; jia bao shan ; yu ji yang
..............page:199-203,209
Study of Risk Acceptance of Nuclear Power
shi zhen gang ; zhang zuo yi ; xue lan
..............page:193-198