Atomic Energy Science and Technology 2009 Issue z2 Measures and Characteristics of Cooling at Shutdown Mode for China Advanced Research Reactor

Measures and Characteristics of Cooling at Shutdown Mode for China Advanced Research Reactor
zhuang yi ; ke guo tu ; liu tian cai ; huang xing rong ; lai tao tao ; yao cheng zhi

..............page:412-416

Numerical Simulation of Temperature and Velocity Fields in Narrow Rectangular Channel for China Advanced Research Reactor
zhou tao ; zhang ji gang ; wang ruo su ; zhang ya pei

..............page:264-267

Analysis of Electromagnetic Field of Direct Action Solenoid Valve With Current Changing
liu qian feng ; bao han liang ; qin ben ke

..............page:330-333

Impact of Helium Impurities on Intermediate Heat Exchanger Materials
ma yan xiu ; yang xiao yong ; ye ping ; wang jie

..............page:301-305

Unqualified Occurrences Finding and Dealing for Stainless Pipe Connection
yang da wei ; ye lin ; huang hong wen ; duan shi lin

..............page:383-385

Pneumatic Conveying Technology Development and Application on High-Temperature Gas-Cooled Reactor
li lin ; chen feng ; huang zhi yong ; zhang hai quan

..............page:394-399

Control of Shortcoming in Nuclear Engineering Construction
zhang zhi hua ; deng ; liu yao guang ; qian da zhi ; xu xian qi ; zhou wei

..............page:386-388

Test for Drying Heavy Water System of Nuclear Reactor
ye lin ; huang hong wen ; qian da zhi ; yang da wei ; zhou shan

..............page:346-349

Analysis of General Configuration of Pool Type Research Reactor Loop System
huang xing rong ; zhuang yi ; zhang jin shan ; han hai fen ; li qing ; yuan lv zheng ; yi da yong

..............page:350-354

Analysis of Discharge Activity Thresholds of Liquid Waste Discharge System for Qinshan Nuclear Power Plant PhaseⅡ Extension Project
zhao guang hui ; yuan xia ; zhao xia

..............page:342-345

Nozzle Loads Optimizing of Inlet Primary Loop Piping in China Advanced Research Reactor
dai shou tong ; wang jun ; han zhi ; jing dan

..............page:275-278

Helium Circulator Supported by AMB for HTR-10 Thermal Test
zhao gang ; ma yan xiu ; fu xiao ming ; wang jie ; yu su yuan

..............page:252-255

Application of SRAC System on China Advanced Research Reactor
lv zheng ; shen feng ; sun zhi yong ; yuan lv zheng

..............page:407-411

Effects of Compressive Stresses on Coefficient of Thermal Expansion of Fine-Grained Isotropic Graphite
zhou xiang wen ; wang hong tao ; dong jian ling ; sun li bin ; yu su yuan

..............page:268-270

Development of Nuclear Powered System
ma yun feng ; zhao fu yu

..............page:197-200

Post-Earthquake Comprehensive Inspection and Assessment of Performances of Nuclear Facility
gao quan yuan

..............page:379-382

Rod-Dropping Test of New Control Rod Movable Loop Electromagnetism Driving Route
zhang zhi hua ; deng ; qian da zhi ; liu han gang ; liu yao guang ; xu xian qi ; zhou wei

..............page:319-322

Production of Radioisotope Thermal Fuel by Reactor and Its Application
huang zhi yong ; jiang sheng yao ; zhou zi peng ; wu zhi fei ; liu yi si ; zhou shi xin

..............page:400-403

Neutronics Study on Hybrid Reactor Cooled by Helium, Water and Molten Salt
li zai xin ; feng kai ming ; zhang guo shu ; zheng guo yao ; zhao feng chao

..............page:223-226

Heat Transfer and Pressure Loss of Immediate Heat Exchanger
yu xiao li ; yang xiao yong ; wang jie

..............page:256-259

Design of Core Vessel and Core Structure in China Advanced Research Reactor
fan yue rong ; zhang zhan li ; shi chen lei ; dai chang nian ; lang rui feng ; sun lin zhi

..............page:309-311

Analysis of Effect on Main Pump Startup With Slow Speed due to Thermal Expansion Difference of Graphite Guide Liner
wang zuo ; wang shi tao ; yu zhong bin

..............page:334-337

Tactics and Challenge to Electromagnetic Compatibility in Nuclear Power Plant
qiu jian wen ; kong hai zhi ; mo guo jun

..............page:360-363

Primary Design and Safety Analysis of Multi-application Integrated Light Water Reactor
liu jian ge ; peng min jun ; jiang li guo

..............page:210-214

Experimental Research of Residual Heat Removal Safety in Pulsed Reactor
zhao zhu min ; chen li xin ; zhu yang ni ; yuan jian xin ; zhu guang ning ; wei jia xiang ; wen hai bing

..............page:338-341

Zero Leakage Circulation Pump for New Type Reactor
deng li ping ; xue kuan rong

..............page:279-282

Experimental Study on Pulsed Reactor With Steady Core Arrangement at Pulse Operation Mode
chen li xin ; zhao zhu min ; yuan jian xin ; chen da ; zhu guang ning ; jiang xin biao

..............page:240-243

Study of Magnetic Vortex Damper Used by Control-Rod System of High-Temperature Gas-Cooled Reactor
zhang wei ; diao xing zhong

..............page:326-329

Analysis and Experiment of New Style Discharge Vessel in Reserve Shutdown System of High-Temperature Gas-Cooled Reactor
yang fan ; huang zhi yong ; he xue dong ; zhang pu ; li lin ; chen feng

..............page:297-300

Analysis and Calculation of Structure Strength of Hot Gas Duct in HTR-PM
zhang li ; he shu yan ; wu zuo zuo ; liu jun jie

..............page:271-274

Water Ingress Accident of 250 MW Pebble-Bed Modular High-Temperature Gas-Cooled Reactor
zheng yan hua ; wang yan ; shi lei

..............page:232-235

Application of Plate Heat Exchanger in Heavy Water System of Research Reactor
han hai fen ; zhang jin shan ; huang xing rong ; zhuang yi

..............page:312-315

Research Status and Progress of U-Mo Alloy Fuel in Nuclear Power Institute of China
yin chang geng ; chen jian gang ; sun chang long ; liu yun ming ; pang xiao xuan ; sun xu dong

..............page:389-393

Erection Discussion of Nuclear Safety Pipes in Reactor
liu ji hua ; zhang zhi hua ; xu xian qi

..............page:323-325

Development of Integrated Nuclear Heating Reactor Ⅱ and Its Application Prospect
li wei hua ; zhang ya jun ; guo ji lin ; zheng wen xiang

..............page:215-218

Analysis of Absorbed Dose Distribution in Equivalent Model of Head in Case of Operation for Boron Neutron Capture Therapy
zhu yang ni ; jiang xin biao ; zhang qiang ; zhang ji hong ; chen wei ; zhao zhu min

..............page:404-406

Probabilistic Safety Assessment Framework of Pebble-Bed Modular High-Temperature Gas-Cooled Reactor
liu tao ; tong jie juan ; zhao jun ; cao jian zhu ; zhang li guo

..............page:364-366

Man-Machine Interface Design of Real-Time Hardware-in-Loop Simulation System for Power Regulation of Nuclear Heating Reactor
ni xiao li ; huang xiao jin ; dong zhe

..............page:355-359

Characteristic Behavior of Pebble-Bed Modular High-Temperature Gas-Cooled Reactor During Loss of Forced Cooling Accidents
shi lei ; zheng yan hua

..............page:236-239

Physics Experimental Study for Reactor of In-hospital Neutron Irradiator
li yi guo ; xia pu ; zou shu zuo ; zhang yong bao ; lv zheng ; zhu guo sheng ; zheng wu qin ; shi yong qian ; zhou yong mao

..............page:201-203

Study on Stopping Behavior of Primary Helium Circulator for High-Temperature Gas-Cooled Reactor
wang hong ; zhang ming ; zhou hui zhong

..............page:294-296

Source Term in Severe Accident Induced by Small Break Loss of Coolant Accident for AP1000
huang gao feng ; li jing xi ; cao xue wu

..............page:371-374

Research of Hafnium Characteristic for Control Rod of Reactor
huang hong wen ; wu yu ; ye lin ; yang da wei

..............page:316-318

Development and Validation for Fusion-Fission Hybrid Reactor Codes
shao zeng ; cheng he ping ; liang zhi

..............page:244-247

Discussion on Amount of Water Ingress Mass in Steam Generator Heat-Exchange Tube Rupture Accident of High-Temperature Gas-Cooled Reactor
wang yan ; zheng yan hua ; shi lei ; li fu ; sun xi ming

..............page:227-231

Source and Effect of Tritium From Indirect Closed Brayton Cycle With High-Temperature Gas-Cooled Reactor
ye ping ; yang xiao yong

..............page:367-370

Brief Introduction to Engineering and Experiment of HL-2A Tokamak
li qiang

..............page:204-209

In-Pile Sample Value Calculation With MCNP Code
zhu yang ni ; zhao zhu min ; chen li xin ; jiang xin biao

..............page:306-308

Preliminary Study on Electromagnet Drive Mechanism in Reserve Shutdown System of High-Temperature Gas-Cooled Reactor
chen wen hu ; huang zhi yong ; li sheng qiang

..............page:283-287

Thermal Stress Analysis of Uranium Solution Critical Facility
dai shou tong ; liu zhen hua ; zhu qing fu ; han zhi ; wang jun ; jing dan

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

Experimental Study on Enhanced Boiling Heat Transfer
li yong ; yan chang zuo ; liu jia

..............page:248-251

Design Research of Fusion-Fission Hybrid Reactor
cheng he ping ; shao zeng ; liang zhi ; huo xiao dong ; li jun jie

..............page:219-222

Design Scheme on Distributed Control System of HTR-10
ma tao ; wei li qiang ; zhang liang ju ; chen xiao ming

..............page:288-293

Build of Experiment Device About Municipal Secondary Effluent Fouling and Preliminary Experiments
zhang jie ; wu zuo zuo ; shi lin

..............page:417-420

~(14)C Production and Release Behaviour in HTR-PM
chen xiao ; li hong ; cao jian zhu

..............page:375-378