Nuclear Power Engineering 2008 Issue 6 Design and Development of Virtual TXP Control System Software

Design and Development of Virtual TXP Control System Software
WANG Yun-wei;LENG Shan;LIU Zhi-sheng;WANG Qiang;Shang Yan-xia

..............page:128-131

Loose Part Monitoring System for Nuclear Power Plants Based on Virtual Instrument
PAN Shi-biao;LIU Cai-xue;HE Shao-qun;HU Jian-rong;LI Xiang;ZHENG Wu-yuan;WANG Cheng-yuan

..............page:125-127

Stress Relaxation Performance and Prediction Models for Bolt Material of 1Cr10NiMoW2VNbN
GUO Jin-quan;XUAN Fu-zhen;HE Lei

..............page:119-124

Aging Management of Steam Generator in Qinshan Nuclear Power Plant
TAO Jun;WEI Wen-bin;LI Shi-wei

..............page:115-118

Life Management of Reactor Pressure Vessel at Qinshan Nuclear Power Plant
KONG De-ping;LI Hua;ZHENG Hong-lian

..............page:110-114

First Ten-Yearly Modification Study for Daya Bay Nuclear Power Plant
LU Xiu-sheng

..............page:106-109,124

Design of Regulator for n/γ in Complicated Radiation Field
LI Jun-jie;QIU Dong;DU Jin-feng;WANG Qiang

..............page:102-105

Preliminary Design of Sub-Critical Verification Facility for Accelerator Driven System with Auxiliary Shut-Down System
YU Tao;LI Xiao-hua;ZHOU Cheng-long;XIE Qin;MA Zhi-yuan;LIU Ping

..............page:98-101

Development of Augmentation Mechanism for Large Reactivity Step in CFBR-II Reactor
YE Cen-ming;ZHANG Yi;RONG Ru;HU Qian

..............page:95-97,101

Design of Scaler Protector for Reactor
LU Yi;LI Meng;RONG Ru

..............page:66-69,94

Calculation of Displacement Damage Based on Average Displacement Kerma Factor Method
ZOU De-hui;QIU Dong

..............page:62-65

Study on Pull-out Force in Tube-and-Shell Heat Exchangers with Finite Element Method
WANG Jian-ping;JIN Wei-ya;WANG Xiu-min;GAO Zeng-liang

..............page:58-61

Numerical Simulation of Surface Crack Growth on Overlap of Hot-wall Hydrogenation Reactor
LIU Bin;SHEN Shi-ming

..............page:54-57

Signal Process and Profile Reconstruction of Stress Corrosion Crack by Eddy Current Test
ZHANG Si-quan;CHEN Tie-qun;LIU Gui-xiong

..............page:50-53,65

Study on Axial Surface Cracks inside Optimal Autofrettaged Thick Cylinder
ZHENG Xiao-tao;YU Jiu-yang;LIU Yu-hua;LU Xia;WANG Wei

..............page:46-49,57

Experimental Investigation of Conevection Heat Transfer of CO2 at Supercritical Pressures in a Vertical Circular Tube at High Re
LI Zhi-hui;JIANG Pei-xue

..............page:41-45

Numerical Analysis of Crosswind Effect on Wet Cooling Tower Aerodynamic Field
ZHAO Yuan-bin;SUN Feng-zhong;WANG Kai;GAO Ming;YAN Sheng-Ping;GAO Tao

..............page:35-40

Effect of Inlet Parameters on Maximum Discharge Pressure of Boost Installation for Steam-Water Two-Phase Flow
LI Gang;YUAN Yi-chao;LIU Yu-zheng

..............page:30-34

Analysis of Pipeline Virbation Induced by Water Hammer
LI Song;MA Jian-zhong;GAO Li-xia;HU Yong-tao

..............page:25-29

Active Nucleation Site Density during Subcooled Flow Boiling at Vertical Narrow Rectangular Channel
PAN Liang-ming;ZHANG Jun-qi;YUAN De-wen;CHEN De-qi;WANG Xiao-jun

..............page:21-24,34

Simulation Calculation of Response to Linear Positive Reactivity Inserted in Reactor with Temperature Feedback
SHANG Xue-li;ZHANG Fan;CHEN Wen-zhen;ZHAO Lei

..............page:17-20

Measurement of Prompt Neutron Decay Constant on Uranium-Plutonium Metal Assembly
LIU Xiao-bo;FAN Xiao-qiang;YANG Cheng-de;Deng Men-cai

..............page:14-16

A General Formula Considering one Group Delayed Neutron under Nonequilibrium Condition
LI Hao-feng;CHEN Wen-zhen;ZHU Qian;LUO Lei

..............page:10-13,29

Calculation of Fission Rate in CFBR-II Reactor
DU Jin-feng

..............page:6-9

Calculation and Application of Discontinuity Factors in Control Rod Region for High Temperature Gas-Cooled Reactor
ZHOU Xu-hua;LI Fu;WANG Deng-ying;YAN Jian-qiu;LV Wei-feng;HAN Ren-yu

..............page:1-5,9

Research of Pneumatic Control Transmission System for Small Irradiation Samples
BAI Zhong-xiong;ZHANG Hai-bing;RONG Ru;ZHANG Tao

..............page:91-94

One Method for Assessing Internal Dose Due to Tritium
MAO Yong;WANG Xiao-dong

..............page:87-90

Radiation Embrittlement Surveillance of ReactorPressure Vessel
XIAO Bing-shan;ZHANG Le-fu

..............page:83-86

Design of Multi-Channel Amplitude Analyzer Based on LonWorks
ZHANG ying;ZHAO Li-hong;CHEN Ai-hua

..............page:79-82,105

Design of Period Measurement Instrument for Fast Neutron Criticality Facility Based on Virtual Instrument Technology
LI Meng;HU Qian;HU Jin-quan

..............page:74-78

Temperature Correction for Stress Measurement in Fast Burst Reactor
QIU Dong;YIN Yan-peng

..............page:70-73,90