Home|Journal Papers|About CNKI|User Service|FAQ|Contact Us|中文
Full-Text Search:
Nuclear Science and Engineering
FQ: 季刊
AD of Publication: 北京市
Lanuage: 中文;
ISSN: 0258-0918
CN: 11-1861/TL
YP: 1981
Url: 中国核学会
Recommended Journals
Nuclear Science and Engineering
2010 -01
Catalog
Research on ideal steady-state programming control strategy of integrated PWR XU Wen-qi,PENG Min-jun,LIU Jian-ge,JIANG Li-guo(Nuclear Safety and Simulation Technique National Defense Key Subject Laboratory,Harbin Engineering University,Harbin of Heilongjiang Prov.150001,China)
Modeling and simulation of pressurizer dynamic process in PWR nuclear power plant MA Jin,LIU Chang-liang,LI Shu-na (North China Electric Power University,Baoding of Hebei Prov.071003,China)
The first rushing of CEFR turbine ZHANG Ya-bo,ZHANG Dong-hui(China Institute of Atomic Energy,Beijing 102413,China)
Design features for mitigating SGTR of EPR ZHENG Hua(China Nuclear Power Engineering Co.Ltd.,Shenzhen of Guangdong Prov.518045,China)
An experimental investigation of bubble growth and effects on heat transfer in water subcooled flow boiling in a vertical narrow rectangular channel CHEN De-qi 1,PAN Liang-ming 1,YUAN De-wen 1,WANG Xiao-jun 2(1.School of Power Engineering,Chongqing University,Chongqing of Sichuan Prov.400044,China;2.Institute of Nuclear Power of China,Chengdu of Sichuan Prov.610041,China)
Numerical heat transfer in cylindrical nuclear reactor with reflected layer LIU Hui-juan,ZHANG Min,PENG Wen-jie(School of Power Engineering,Nanjing University of Science & Technology,Nanjing of Jiangsu Prov.210094,China)
Present status of ultra-cold neutron (UCN) source constructions YU Xiao-ling,FENG Qi-xi,FENG Quan-ke(School of Energy and Power Engineering,Xi'an Jiaotong Universty,Xi'an of Shannxi Prov.710049,China)
The dynamic reliability analysis for the CEFR nuclear-cycle cooling water based on GO methodology YANG Li-Fang,YANG Hong-Yi(China Institute of Atomic Energy,Beijing 102413,China)
Thermal-hydraulics design and analysis of water-cooled energy production blanket for a fusion-fission hybrid reactor JIN Ming1.2,JIANG Jie-qiong1.2,LIU Song-lin1.2,WANG Ming-huang1.2,BAI Yun-qing1.2,WU Yi-can1.2,FDS Team1.2 (1.Institute of Plasma Physics,Chinese Academy of Sciences,Hefei of Anhui Prov.230031,China;2.School of Nuclear Science and Technology,University of Science and Technology of China,Hefei of Anhui Prov.230027,China)
Neutronics design and analysis of water-cooled energy production blanket for a fusion-fission hybrid reactor JIANG Jie-qiong1.2,WANG Ming-huang1.2,CHEN Zhong1.2,QIU Yue-feng1.2,LIU Jin-chao1.2,WU Yi-can1.2,FDS Team1.2(1.Institute of Plasma Physics,Chinese Academy of Sciences,Hefei of Anhui Prov.230031,China;2.School of Nuclear Science and Technology,University of Science and Technology of China,Hefei of Anhui Prov.230027,China)
Development of design and analysis software for advanced nuclear systems WU Yi-can1.2,HU Li-qin1.2,LONG Peng-cheng1.2,LUO Yue-tong1.2,LI Ya-zhou1.2,ZENG Qin1.2,LU Lei1.2,ZHANG Jun-jun1.2,ZOU Jun1.2,XU De-zheng1.2,BAI Yun-qing1.2,ZHOU Tao1.2,CHEN Hong-li1.2,PENG Lei1.2,SONG Yong1.2,HUANG Qun-ying1.2,FDS Team1.2(1.School of Nuclear Science and Technology,University of Science and Technology of China,Hefei of Anhui Prov.230027,China;2.Institute of Plasma Physics,Chinese Academy of Sciences,Hefei of Anhui Prov.230031,China)
Assessment procedure and probability determination methods of aircraft crash events in siting for nuclear power plants ZHENG Qi-yan1,ZHANG Li-jun1,HUANG Wei-qi1,YIN Qing-liao2(1.Department of Nuclear Defence,Institute of Chemical Defense,Beijing 102205,China;2.China Nuclear Engineering and Construction Corporation,Beijing 100037,China)
2010 Issues:  [01] [02] [03] [04] [S1]
More Issues:   [1992]   [1993]   [1994]   [1995]   [1996]   [1997]   [1998]   [1999]   [2000]   [2001]   [2002]   [2003]   [2004]   [2005]   [2006]   [2007]   [2008]   [2009]   [2011]   [2012]   [2013]   [2014]   [2015]   [2016]   [2017]
©2006 Tsinghua Tongfang Knowledge Network Technology Co., Ltd.(Beijing)(TTKN) All rights reserved