0258-0926
2004 Issue 1
Correlation between Code Threshold/Criteria and Ultrasonic Testing Data Analysis Method in Reactor Vessel In-service Inspection
li su jia ; nie yong ; xu yuan huan
li su jia ; nie yong ; xu yuan huan
..............page:1-3
Performance Monitoring and Fault Diagnosis about Flow Passage of Turbines in Nuclear Power Plant
jiang ning ; li zheng
jiang ning ; li zheng
..............page:4-7
New Idea for Thermal Parameters Fault Diagnosis of Nuclear Power Steam Turbine System Based on Large-scale Off-design Mathematic Model
cui da long ; li zheng
cui da long ; li zheng
..............page:8-12,26
Transient Mixing Characteristic of Reactor Pressure Vessel under Pressurized Thermal Shock
wang hai jun ; chen ting kuan ; luo zuo shan ; lu dong hua ; sun ying xue
wang hai jun ; chen ting kuan ; luo zuo shan ; lu dong hua ; sun ying xue
..............page:13-17
Effect of 2MeV Proton Radiation on the Microstructure in Zircaloy 4
zu xiao tao ; zhu sha ; wang lu zuo ; you li ping ; wan fa rong
zu xiao tao ; zhu sha ; wang lu zuo ; you li ping ; wan fa rong
..............page:50-53
Design,Test and Operation of Helium Circulator for HTR-10
zhou hui zhong ; wang jie ; tang quan fa
zhou hui zhong ; wang jie ; tang quan fa
..............page:54-58
Study on the Impeller Hydraulic Performance for the Contra-Rotating Axial Flow Pump
wang de jun ; zhou hui zhong ; huang zhi yong
wang de jun ; zhou hui zhong ; huang zhi yong
..............page:59-63
Application of PLC in the Crane Control System of MJTR
li zi qiang ; ji xiang dong
li zi qiang ; ji xiang dong
..............page:64-66,90
Design of Harmonic Screw-driven Stop Valve for Nuclear Power Units
wang xiang jiang
wang xiang jiang
..............page:67-69
"Primary-Least Structure" Method as a Stress Categorization Tool for Design by Analysis
liu xiao long ; jiang jia ling
liu xiao long ; jiang jia ling
..............page:70-73
Numerical Simulation of the Stress Distribution for Fast Burst Reactor Under Pulsed Operation
qiu dong
qiu dong
..............page:74-78,82
Aging Management Methods for Nuclear Power Plant Components
wang lu shuai ; zhou gang
wang lu shuai ; zhou gang
..............page:79-82
..............page:83-85
..............page:86-90
..............page:91-92,96
Neutron Spectra and Fluence of CFBR-II Reactor Measured by Foils Activation Technique
zheng chun ; wu jian hua ; li jian sheng ; wang qiang ; he zhao zhong ; huang yi chao ; dai shao feng
zheng chun ; wu jian hua ; li jian sheng ; wang qiang ; he zhao zhong ; huang yi chao ; dai shao feng
..............page:93-96
Shannon Entropy Characteristics of Two-phase Flow Density Wave Instability Experiments for 200MW Nuclear Heating Reactor
shi lei ; zhang zuo yi ; gao zu zuo
shi lei ; zhang zuo yi ; gao zu zuo
..............page:18-21
Experiments of Pool Boiling Heat Transfer Enhancement of Water-Based Magnetic Fluid
liu jun hong ; gu jian ming ; lian zhi wei ; yan zhi meng ; liu hui
liu jun hong ; gu jian ming ; lian zhi wei ; yan zhi meng ; liu hui
..............page:22-26
Research Progress on Passive Safety System of Advanced PWR
xiao ze jun ; zhuo wen bin ; chen bing de ; bai xue song ; jia dou nan
xiao ze jun ; zhuo wen bin ; chen bing de ; bai xue song ; jia dou nan
..............page:27-31
Technical Study of Real-time Simulation System for Digital I&C System of Steam Generator in Nuclear Power Plant
shi zuo ; jiang ming zuo ; ma yun qing
shi zuo ; jiang ming zuo ; ma yun qing
..............page:32-36
Study on Water Level Detector Composed of Encoded Thermal Resistance
zhang hong zhong ; wang wen ran ; liu zhi yong ; duan quan sheng
zhang hong zhong ; wang wen ran ; liu zhi yong ; duan quan sheng
..............page:37-40,44
Preparation of Micro Carbide Spheres by Gas Grinding
long chong sheng ; qiu bang chen ; ying shi hao
long chong sheng ; qiu bang chen ; ying shi hao
..............page:41-44
Random Cyclic Constitutive Models of 0Cr18Ni10Ti Pipe Steel
zhao yong xiang ; yang bing ; li peng zhou
zhao yong xiang ; yang bing ; li peng zhou
..............page:45-49,63