Nuclear Power Engineering 2010 Issue 2 Research on Application of Complex-Genetic Algorithm in Nuclear Component Optimal Design

Research on Application of Complex-Genetic Algorithm in Nuclear Component Optimal Design
he shi jing ; yan chang zuo ; wang jian jun ; wang meng

..............page:122-125,135

Reliability Data Process and Analysis of Instrument and Control Switch in Nuclear Power Plants
shi zuo ; zuo deng hua ; shi hai ning ; tu feng sheng

..............page:54-57,66

3D Numerical Analysis and Optimization of Aerodynamic Performance of Turbine Blade
wang ding biao ; xie wen ; zhou jun jie

..............page:98-102,112

Transient Thermal-Hydraulic Characteristics Analysis Software for PWR Nuclear Power Systems
wu ying wei ; zhuang cheng jun ; su guang hui ; qiu sui zheng

..............page:47-49,62

Reduction of Snubber in Nuclear Piping System Based on Numerical Simulation
chen min ; ren chun ling ; wu gao feng ; zhang zhou hong

..............page:103-107

Research on Coupling of COBRA-IV and CFX
liu yu ; zhang hong ; jia bao shan

..............page:43-46

Inlet Flow Analysis in Magnetic-Drive Condenser Pump Based on Numerical Simulation of Flow Field
kong fan yu ; zhang hong li ; gao cui lan ; xue kuan rong

..............page:37-42

Analytic Function Expansion Nodal Method for Hexagonal Geometry Corrected by Discontinuity Factors
ni dong yang ; xian chun yu

..............page:1-5

he dong li gong cheng gao yue

..............page:145

Research on Condition Monitoring Method for Operator Support System
wang he ; cheng shou yu ; zhang zhi jian

..............page:71-75

Oxidation Kinetics of N18 Zirconium Alloy at Temperatures of 600～1200℃ in Steam
liu yan zhang ; qiu jun ; liu xin ; zhao wen jin

..............page:85-88

Method of Dynamic Fuzzy Symptom Vector in Intelligent Diagnosis
sun hong yan ; jiang xue feng

..............page:67-70

Design of Parameter Polling Instrument for Fast Neutron Criticality Facility
hu zuo ; li zuo ; hu jin quan

..............page:63-66

Numerical Simulation on Heat Transfer Enhancement in Shell Side of Shell-and-Tube Heat Exchanger with Leading Type Shutter Baffles
gu xin ; dong qi wu ; liu min shan ; zhou ya ning

..............page:113-117

Study on Sorption Capacity and Characterization of Sr2+ on Synthetic Zeolite
wang jin ming ; yi fa cheng

..............page:89-93

Digitization and Simulation Realization of Full Range Control System for Steam Generator Water Level
qian hong ; ye jian hua ; qian fei ; li chao

..............page:58-62

Failure Analysis of Cold Neutron Source In-Pile Parts
tang feng ping ; hu chun ming

..............page:29-32

Three Dimension Neutron Transport Characteristics Method Code (Ⅰ)——Interpolation Treatment of Boundary Condition
chai xiao ming ; yao dong ; wang zuo

..............page:11-15

Simulation of Oxidation in HTR-10 Core
yu xin li ; zuo xiao wei ; yu su yuan

..............page:81-84,97

Strategy for Steam Generator Tube Rupture Accident with Total Loss of Pressurizer Spray
lu xiang zuo ; jiang xiao hua ; wang zuo ; ou yang yong

..............page:21-23,28

Feasibility Study on NPP Loading Pattern Search via Direct Optimization Method
xu hua ; jiang xiao feng ; zhang shao zuo

..............page:131-135

Analysis of Fire Frequency in Nuclear Power Plants
hu xiao min

..............page:76-80

Power Spectrum Density Analysis System of 252Cf Neutron Signals
ren yong ; mi de ling ; wei biao ; feng peng

..............page:140-144

Experimental on Metering Characteristics of Multi-hole Orifice
ma tai yi ; wang dong ; zhang bing dong ; lin zong hu

..............page:126-130

Mathematical Modeling and Simulation Research of New Type Sodium Pump Based on Superconduct
yang zhi da ; zuo heng bo ; wu hong jun ; sun hao wei ; han wei shi

..............page:118-121,130

Mathematic Model for Nuclear Power Station with Integrated Secondary-Loop
xu shi jie ; lin meng ; yang yan hua ; cheng xu

..............page:50-53

Three Dimension Neutron Transport Characteristics Method Code(Ⅱ)——Numerical Verification
chai xiao ming ; yao dong ; wang zuo

..............page:16-20

Design of Vacuum Releaser of the Primary Circuit of LingAo Nuclear Power Plant
li chun mei ; luo ming kun ; li shu zhou ; niu wen hua ; yang hong ; cui huai ming

..............page:94-97

Pipe Deformation and Dynamic Stress Analysis During Water Hammer
cao yuan ; jin xian long ; du xin guang

..............page:33-36,42

Verification and Validation of Multi-Group Library MUSE1.0 Created from ENDF/B-VII.0
chen yi xue ; chen chao bin ; wu jun ; yang shou hai ; zhang bin ; lu dao gang

..............page:6-10,15

Criticality Calculations of Burnup-Credit Spent Fuel Storage Pool for Nuclear Power Plants
zhang pu zhong ; chen yi xue ; ma xu bo ; mao ya wei ; shi sheng chun ; zhang bin

..............page:24-28

A Discussion on Variation of RCC-M 2007
li xiao yan ; hu yan ; gao rui

..............page:108-112

Locomotion Precision and High-speed Stop Effect for Reactivity Stepping Mechanism of CFBR-II
ye zuo ming ; zhang yi ; sun wen qing ; jiang zhi guo

..............page:136-139