姓名:陈志
职称:副教授,科研办主任
电话:0551-63606142
传真:0551-63607713
邮箱:zchen#ustc.edu.cn
网站:
陈志:男,博士,副教授,硕士生导师,1972年出生于四川省通江县。2005-2008年间于核工业西南物理研究院获得硕士和博士学位。在《Nuclear Fusion》、《Fusion Engineering and Design》等SCI、EI学术刊物上合作发表论文30余篇。在《中日CUP计划》项目支持下曾前往日本富山大学同位素中心做学术访问。目前承担多项国家级科研项目,指导在读硕士研究生3名。参加和组织国际国内会议多次。
科研方向:
反应堆及包层设计与技术、辐射防护与环境保护、反应堆安全与环境以及氢同位素热动力特性等多学科交叉研究。
科研成果:
1)在国内国际学术期刊及国际会议上发表学术论文30余篇;
2)第八届IAEA聚变电站安全会议口头报告;
3)第二届IAEA第一代聚变电站技术会议口头报告;
4)第九届中日先进聚变裂变材料技术会议口头报告。
近期发表论文:
1.M.Matsuyama,K.Shinmura,Z.Chen,and Y.Torikai,Solubility of Tritium in Cu-Be Alloy,9th International Conference on Tritium Science and Technology: TRITIUM 2010;
2.M.Matsuyama,Z.Chen,K.Nisimura et al,Trapping and depth profile of tritium in surface layers of metallic materials,10.1016/j.jnucmat.2011.04.005.
3.Zhi Chen,K.M.Feng,Z.W.Zhou et al,Safety assessment of Chinese ITER TBM design with helium-cooled solid breeder concept,Nucl.Fusion Vol.47 (2007)S442ndash;S446;
4.Zhi Chen,K.M Feng,G.S.Zhang,T.Yuan and C.H.Pan,Preliminary safety research for CH HCSB TBM based on FMEA method,Fusion Engineering and Design,2008 (Accepted);
5.陈志、邓柏权、冯开明等,先进燃料聚变反应性增强的新机制,《物理学报》 Vol.55,No.4,(2006),p1724-1730;
6.Chen Zhi,Deng Baiquan,Feng Kaiming,et al,An ingenious approach of determining hydrogen isotope solubilities,diffusivities and permeabilities in GWHER-1 stainless steel,Chinese Physics,Vol 15.No 7,(2006)p1492-1497;
7.陈志、冯开明、张国书、袁涛等,ITER实验包层模块活化计算与环境安全分析,《核聚变与等离子体物理》Vol.25,No.3,(2005)p183-188;
8.Chen Zhi,FENG Kai-ming,ZHANG Guo-shu et al,Activation and afterheat analysis for CH HCSB TBM,Nuclear Fusion and Plasma Physics Vol.26,No.3 (2006)p176-180;
9.Chen Zhi,Feng Kaiming,et al,Preliminary Safety Research for CH HCSB TBM based on FMEA Method,Ninth China-Japan Symposium (CJS-9)on Materials for Advanced Energy Systems and Fission ; Fusion Engineering,Oct.22-26,2007,Guilin,China;
10.Zhi Chen,K.M.Feng,G.S.Zhang,H.B.Liu and T.Yuan Preliminary Failure Mode and Effect Analysis on Chinese ITER Helium Cooled Solid Breeder Test Blanket Design Concept,2nd IAEA Technical Meeting on First Generation of Fusion Power Plants:
Design ; Technology,Vienna,20 ndash; 22 June,2007;
11.Zhi CHEN,Kaiming FENG,Safety assessment of Chinese ITER TBM design with helium-cooled solid breeder concept,IAEA 8th Technical Meeting on Fusion Power Plant Safety,2006.7.10-14,in Vienna.
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