Chinese Journal of Nuclear Science and Engineering 2014 Issue 4 Study on Determination of Trace Zinc in Primary Circuit of PWR

Study on Determination of Trace Zinc in Primary Circuit of PWR
MI Zheng-feng;HUANG Wen-jie;XU Chi;China Institute of Atomic Energy;

..............page:433-436+443

Mixed Movement Characteristics of Condensation Water and Steam in CEFR Three Loop Deaerator
YANG Yong-chang;ZHANG Lu;LIU Fu-chen;China Institute of Atomic Energy;

..............page:437-443

Improvement of Feedwater Control System of Supercritical Water Cooled Fast Reactor
HE Yun-tian;PENG Chang-hong;CHEN Huan;Nuclear Instrument Company of Xi’an Nuclear Instrument Factory;School of Nuclear Science and Technology;University of Science and Technology of China;

..............page:444-447+461

Neutronics Analysis of the Heat Piped Lithium Cooled Space Fast Reactor
WANG Li-peng;JIANG Xin-biao;ZHAO Zhu-min;ZHANG Xin-yi;CHEN Li-xin;Northwest Institute of Nuclear Technology;

..............page:448-453

Fabrication and Validation of PWR MATXS Nuclear Data Library
HUO Xiao-dong;China Nuclear Power Engineering Co.;Ltd.;

..............page:454-461

Analysis of Hydrodynamic Force of the Primary Loop under LOCA Condition
TANG Qiong-hui;ZHOU Rui;WU Ying-xi;WANG Rong-zhong;China Nuclear Power Design Company;Shenzhen of Guangdong Prov.;

..............page:462-468+474

Study on the Calculation Method of Source Term from Fission Products
ZHOU Jing;GONG Quan;QIU Hai-feng;Shanghai Branch of China Nuclear Power Technology Research Institute;

..............page:469-474

Calculation and Analysis of the Source Term of the Reactor Core Based on Different Data Libraries
CHEN Hai-ying;ZHANG Chun-ming;WANG Shao-wei;LAN Bing;LIU Qiao-feng;HAN Jing-ru;Nuclear and Radiation Safety Center;MEP;

..............page:475-481+487

Effect of PWR Coolant Environment on the Fatigue Life of Reactor Equipment Materials
SUN Hai-tao;WANG Chen;XIONG Dong-qing;WANG Qing;FANG Yong-gang;ZHANG Yue;SUN Zao-zhan;Nuclear and Radiation Safety Center;SEPA;

..............page:482-487

Effect of Temperature on Oxygen Concentration Change in Static Lead-bismuth Eutectic
ZHANG Min;WU Bin;GAO Sheng;WANG Yan-qing;WU Xin;HUANG Qun-ying;FDS Team;University of Science and Technology of China;Institute of Nuclear Energy Safety Technology;Chinese Academy of Sciences;

..............page:488-493+499

Study on Thermal Expansion and Aging Performance of Lead-bismuth Eutectic
XU Jing-yao;WANG Long;XU Gang;LIU Shao-jun;HUANG Qun-ying;FDS Team;University of Science and Technology of China;Institute of Nuclear Energy Safety Technology;Chinese Academy of Sciences;Hefei University of Technology;

..............page:494-499

Design and Implementation of Parallel Computing on Monte Carlo Fixed Source Calculation
CHEN Cheng;SONG Jing;ZHANG Kuan;SUN Guang-yao;HAO Li-juan;ZHENG Hua-qing;WU Yi-can;University of Science and Technology of China;Institute of Nuclear Energy Safety Technology;Chinese Academy of Science;

..............page:500-504+510

Modeling and Analysis of Transient Thermal Hydraulic Characteristic for Natural Circulation Type Steam Generator
QIU Gui-hui;China Nuclear Power Design Company Ltd.;

..............page:505-510

Development of a Multi-functional Platform to Perform the I&C System Test,Diagnosis and Training
REN Chun-xiang;WANG Xing-ye;GUAN Yun-quan;Jiangsu Nuclear Power Cooperation;AREVA NP GmbH;

..............page:511-515+523

Analysis of Source Term under Containment Failure Severe Accident Induced by SB– LOCA
GUO Ding-qing;TONG Li-li;China Nuclear Power Design Co.;Ltd.;School of Mechanical and Power Engineering;Shanghai Jiaotong University;

..............page:516-523

Study on Containment Direct Heating(DCH)Severe Accident Phenomena
WANG Gao-peng;YE Zhong-hao;ZHU Wen-tao;China Nuclear Power Engineering Co.;Ltd.;CNNC;State Nuclear Power Engineering Co.;Ltd.;SNPTC;

..............page:524-529

Analysis for the Passive Containment Cooling System of Haiyang NPP under Severe Accident Condition
MA Bai-song;ZHUANG Ya-ping;ZHENG Fu-tao;Shandong Nuclear Power Company Ltd.;

..............page:530-536

Study on Scoping Method for Human Reliability Analysis of Fire PSA
ZHUO Yu-cheng;QIU Yong-ping;HE Jian-dong;Shanghai Nuclear Engineering Research & Design Institute;

..............page:537-540+546

Analyses on Accident Transient of Complete Loss of Forced Reactor Coolant Flow in AP1000
JING Jian-ping;ZHANG Chun-ming;SUN Wei;AN Jie-ru;JIA Bin;Nuclear and Radiation Safety Center;MEP;

..............page:541-546

Study on Radioactive Release of Gaseous and Liquid Effluents during Normal Operation of AP1000
GONG Quan;ZHOU Jing;LIU Yu;Shanghai Branch;China Nuclear Power Design Co.;Ltd.;

..............page:547-553

Development of Nuclear Power Plant Risk Monitor
YANG Xiao-ming;GU Xiao-hui;SUN Jin-long;ZHENG Hao;MA Chao;WANG Lin;BAO Zhen-li;QU Yong;China Nuclear Power Engineering Co.;Ltd.;Jiangsu Nuclear Power Company;Scandpower Inc.;

..............page:554-559

Comprehensive Evaluation and Study on Energy Saving and Emission Reduction of Nuclear Power Based on the Osculation Value Method
LIU Zhi-hui;LIU Xiao-min;WEI Fang-xin;Nuclear and Radiation Safety Center;Ministry of Environmental Protection;Institute of Economics Study;Hebei University of Economics & Business;

..............page:560-568

The Reliability Analysis of the Main Feed Pump Group Based on GO Methodology
LIU Dong;LUAN Xiu-chun;WANG Hu;College of Nuclear Science and Technology;Harbin Engineering University;Science and Technology Research Institute of China Datang Corporation;

..............page:569-572+576

Disposal and Analysis for Range Switch Defect of RPN Intermediate Range
XU Jian-fei;ZHANG Shu-shan;XIAO Yu;PI Li-peng;China Nuclear Power Engineering Company;

..............page:573-576

CHINESE JOURNAL OF NUCLEAR SCIENCE AND ENGINEERING Volume 34 2014

..............page:577-584

he ke xue yu gong cheng zheng gao jian ze

..............page:586