0258-0918
2006 Issue 1
..............page:Ⅰ-Ⅱ
Fusion neutron yield and flux calculation on HT-7 superconducting tokamak
FU Yan-zhang;ZHU Yu-bao;CHEN Jue-quan
FU Yan-zhang;ZHU Yu-bao;CHEN Jue-quan
..............page:28-32,38
Research and development of the automatic modeling system for Monte Carlo particle transport simulation
WU Yi-can;LI Ying;LU Lei;DING Ai-Ping;HU Hai-min;ZENG Qin;LUO Yue-tong;ZHENG Shan-liang;HUANG Qun-ying;CHEN Yi-xue
WU Yi-can;LI Ying;LU Lei;DING Ai-Ping;HU Hai-min;ZENG Qin;LUO Yue-tong;ZHENG Shan-liang;HUANG Qun-ying;CHEN Yi-xue
..............page:20-27,78
Supply risk under the condition of discontinuous demand in the field of nuclear power industry
WEI Qi-yan;TIAN Zhi-long
WEI Qi-yan;TIAN Zhi-long
..............page:15-19,71
Suitability analysis of nuclear power to trading and bidding mechanism in competitive electric market
DING Zhen-xing;LONG San-qiang
DING Zhen-xing;LONG San-qiang
..............page:9-14,8
How to speed up nuclear power development in China
WEN Hong-jun
WEN Hong-jun
..............page:1-8
Structural design and fabrication of dual-functional lithium lead test blanket module for ITER
LIU Song-lin;WANG Wei-hua;LONG Peng-cheng;LI Chun-jing;WU Yi-can
LIU Song-lin;WANG Wei-hua;LONG Peng-cheng;LI Chun-jing;WU Yi-can
..............page:92-96
Thermomechanical analysis of the DFLL test blanket module for ITER
CHEN Hong-li;WU Yi-can;BAI Yun-qing
CHEN Hong-li;WU Yi-can;BAI Yun-qing
..............page:88-91,96
Activation analysis and waste management for the dual functional lithium-lead test blanket module for ITER
CHEN Ming-liang;HUANG Qun-ying;ZHENG Shan-liang;WU Yi-can
CHEN Ming-liang;HUANG Qun-ying;ZHENG Shan-liang;WU Yi-can
..............page:83-87
Decision support system based on knowledge base in Guangdong nuclear power plant
YE Zhi-qiang;XU Jia-shu
YE Zhi-qiang;XU Jia-shu
..............page:79-82,87
Re-evaluation of floor response spectra of reactor building for Daya Bay NPP
LI Zhong-cheng;LI Zhong-xian
LI Zhong-cheng;LI Zhong-xian
..............page:72-78
Application of. NET technique in the invalid report system of nuclear power plant equipment
XU Li;ZHENG Wei;LI He;HAO Bao-shui;WANG Qi
XU Li;ZHENG Wei;LI He;HAO Bao-shui;WANG Qi
..............page:67-71
Design of fast-thermal coupled spectrum sub-critical reactor of accelerator driven system verification facility
YU Tao;SHI Yong-qian;XIA Pu;LIAO Yi-xiang;XIAN Wen-ping;HU Cai-rong
YU Tao;SHI Yong-qian;XIA Pu;LIAO Yi-xiang;XIAN Wen-ping;HU Cai-rong
..............page:63-66,56
Thermal hydraulic analysis of double-side heating once-through steam generator with helical tubes
YU Jian-hui;JIA Bao-shan
YU Jian-hui;JIA Bao-shan
..............page:57-62,50
A conservation-equation-based method to diagnose reactor components faults
TANG Hu;GAO Zu-ying;DONG Yu-jie
TANG Hu;GAO Zu-ying;DONG Yu-jie
..............page:51-56
Experimental study on the coolant flow resistance of control rod channel in research reactor
ZHANG Wei;BO Han-liang;SUN Chang-long;JIA Hai-jun
ZHANG Wei;BO Han-liang;SUN Chang-long;JIA Hai-jun
..............page:46-50
Development and application of random walk model of atmospheric diffusion in emergency response of nuclear accidents
CHI Bing;FANG Dong;LI Hong
CHI Bing;FANG Dong;LI Hong
..............page:39-45
Integral test for 239pu
LIU Ping
LIU Ping
..............page:33-38