Nuclear Power Engineering 2004 Issue 3 Management Self-assessment in Construction Phase of Nuclear Power Station

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Nuclear Power Engineering
0258-0926
2004 Issue 3

Management Self-assessment in Construction Phase of Nuclear Power Station
shao bi xiu

..............page:284-288

Aging Analysis of Reactor Pressure Vessel for Unit 2 of DAYA Bay Nuclear Power Station
wan li hang ; liu peng ; tao yu chun

..............page:252-254

Improvement of Fabrication and Installation Technology for Reactor Pressure Vessel and Steam Generator of Ling'ao Nuclear Power Station
chen zhen wei

..............page:249-251

Thermo-electric Performance Investigation of Two Layer Inhomogeneous Doped Graded Material FeSi2
liu xiao zhen ;z.a.munir; zou cong pei

..............page:246-248,259

Synthetic Analysis for the Probabilistic Models of Cyclic Strain-life Relations of 16MnR Steel
yang bing ; zhao yong xiang ; zuo ping bo ; zeng jing

..............page:241-245

Thermal Expansion of Zr, Zr-4 and New Zirconium Alloys
xue shu juan ; wang yun hui ; zhao wen jin ; ying shi hao

..............page:236-240

Surface Modification of a Ti-2Al-2.5Zr Alloy by N Ion Implantation
zu xiao tao ; feng xiang dong ; deng jiong ; qiu shao yu ; zhou ji meng ; wang zhi guo

..............page:233-235,251

Improvements of Evaporation Drag Model
li xiao yan ; yang yan hua ; xu ji zuo

..............page:230-232,245

An Experimental Investigation of Drag Characteristic of A Hot Particle Moving in Coolant Liquid
chen dong hai ; cao xue wu

..............page:226-229,240

Experimental Study of Critical Heat Flux during Natural Convective Boiling in Inclined Annular Tubes Submerged in Saturated Liquids
liu zhen hua ; zhang tong

..............page:222-225

Visualization Test for Flow Field of Bundles with Grid Spacers
xiong wan yu ; chen bing de ; xiao ze jun ; wang xiao jun

..............page:218-221

Dynamic Responses of Control Rods of Nuclear Ship under Impact Load
zuo xiao wei ; wu hong zuo ; yu su yuan

..............page:214-217

Parallel Algorithm and Software Development for Structure Seismic Response Analysis
li li jun ; jin xian long ; li yuan yin

..............page:210-213

Study on the Progression of Severe Core Damage Induced by SGTR and Mitigation Measures for QINSHAN NPP Unit 1
xu yi quan ; su yun ; cao xue wu

..............page:279-283

Preliminary Study on the Effect of Spray Model on Hydrogen Explosion
lin ji ming ; jia bao shan ; liu bao ting

..............page:275-278,283

Discussion about Design of Front Guide Impeller of Axial Flow Pump
li tong zhuo ; chen jian ; lu hong zuo ; xiang qing jiang

..............page:270-274,283

Discussion on Replacement of Steam Generator
ling xing ; huang su yi

..............page:267-269

Abrasion and Blockage Mechanism of Incore Flux Thimble and Preventive Maintenance Strategy
liu zheng jun

..............page:264-266,269

Design of Passive Heat-switch between Pressure Tube and Calandria Tube of Thorium-based Advanced Nuclear Energy System
you song bo ; yu ji yang ; yang gao sheng

..............page:260-263

Modeling and Steady-state Analysis for a Horizontal Steam Generator
dong yong sheng ; zhang jian min

..............page:255-259

Numerical Simulation Analysis of the Effect of Crud on Flow-rate Distribution of Hot Channel in Plate-type Fuel Core
hu jun ; zhao hua ; jiang xu lun ; chen jun

..............page:207-209,221

Fatigue Analysis of Welded Joint at Tube-plate of Steam Generator in HTR-10
he shu yan ; li xiao tian

..............page:203-206

Theoretical Study in the Fluid-Induced Vibration Analysis of Reactor Core Barrel
mao qing ; zhang jing hui

..............page:198-202

Japanese Small Nuclear Reactors and Their Technical Characteristics
chen bing de

..............page:193-197,202