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Chinese Journal of Nuclear Science and Engineering
0258-0918
2003 Issue 1
zhong guo he xue hui 2003 nian xue shu huo dong ji hua biao
sun jian hua
..............
page:96-96
ATHLET Code and Its Application in Low Temperature Heating Reactor
fang jing ; zhou zhi wei
..............
page:91-95
Research of Fuzzy Control of PWR Nuclear Power System
liu sheng zhi ; cui zhen hua ; you hong jun ; zhang nai yao
..............
page:9-13,31
The Contribution of Nuclear Power Development for CO2 Emission Reductions
zhao ren zuo
..............
page:1-8
Function and Application of the Safety Analysis Code SAC-PREARS for Passive Residual Heat Removal System
liao yi xiang
..............
page:86-90
Overview of Spherical Torus Studies
wang ai ke ; cheng fa yin ; dong jia qi ; li zheng wu
..............
page:79-85,90
Study of Beam Dynamics on High Current 3.5 MeV RFQ for China ADS
guan zuo ling ; luo zi hua ; fu shi nian
..............
page:73-78
Effect of Different Distances Between Plates on Hydrodynamic Characteristics of a Pulsed Column with Baffle Plate
wang yue yun ; wu qiu lin
..............
page:68-72
Effect of Helium on the Irradiation Damage Behaviour in HAZ of Low Activation Fe-Cr-Mn(W,V) Alloy with Higher Performance
hu ben zuo ; mu xia bo si ; gao qiao ping qi lang
..............
page:61-67
Neutron Flux Response to Small Reactivity with Temperature Feedback
cai zhang sheng ; yu lei ; cai zuo
..............
page:58-60
Thermodynamics Design of Regenerative Cycle System in 200 MW Modular HTGR
lin shi yao ; gao zu zuo
..............
page:52-57
Application of Artificial Neural Networks in Analysis of CHF Experimental Data in Tubes
huang yan ping ; dan jian qiang ; chen bing de ; zhu ji zhou ; lang xue mei ; jia dou nan
..............
page:45-51
Application of Wavelet Transform to Fault Diagnosis of Sodium Pump of China Experiment Fast Reactor
feng jun zuo ; wang gui zeng ; xu zuo ; liu guo fa
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page:39-44,57
Study of one Design of Passive Residual Heat Removal System of Nuclear Reactor
yu ji yang ; jia bao shan
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page:32-38
A Measurement Method Regarding Reactor Core Thermal Power and Error Analysis
xu chang rong ; song xiao na ; chen li ming ; yang kun
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page:26-31
The Nonlinear Analysis of Liquid Slug Length Fluctuation in Horizontal Pipe
zhao qing jun ; he li min
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page:20-25
Application of Nonlinear Iteration Semi-analytical Nodal Method in the PWR Fuel Management Calculation
liao cheng kui ; xie zhong sheng
..............
page:14-19