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张国书、陈骝、赵开君、肖池阶、卢新培、孙占学、汤彬、李福生、刘义保、刘云海、李然、杜俊杰、江嘉铭、陈俞钱、张斌、刘腾、王清亚等,偶极场磁约束聚变装置性能特征及研究现状。《中国核电》,第12卷,第5期,2019年10月;
张国书,中国聚变能源的开发现状及新进展,《中国核电》,V.11; No.41(1)26-29, 2018;
张国书,偶极场聚变堆概念特征及研究现状,中国核能技术暨军民融合技术创新发展高端论坛大会特邀报告,海南省海口市,2019.3.21-22;
张国书,聚变-裂变混合堆在我国核能发展的地位及应用前景,福州核能发展技术创新高峰论坛大会特邀报告,2018.6.5-6,福建福州;
张国书,聚变堆中子输运数值模拟技术现状及进展, 2017年核电新技术交流研讨会大会特邀报告,2017.9.14-15,山东威海;
张国书,冯开明,“中国HCSB TBM模块的优化与设计进展”。《核动力工程》第31卷增刊2第107-110页(2010年11月)。
K.M.Feng, C.H.Pan, G.S.Zhang,etc.”Progress on solid breeder TBM at SWIP”.Fusion Engineering and Design (2010)2132-2140.
K.M. Feng, G.S. Zhang, T.Y. Luo …Bin Xiang et al. Progress on Solid Breeder TBM in SWIP. Eighth International Symposium on Fusion Nuclear Technology (ISFNT9), Dalian, China, Oct. 12-Oct. 16, 2009.
G.Zhang,Z.Zhou,K.Feng.”A new modular design concept for China’s HCSB TBM in ITER”. Fusion Engineering and Design (2010)1819-1823.
K.M.Feng,C.H.Pan, G.S.Zhang, X.Y.Wang, G.Hu, Z.Chen, Z.Zhao, T.Yuan, H.B.Liu, Z.Q.Li, C.M.Gao, Q.X.Cao, T.F.Hao, L.H.Ma,J.W.Yang, D.L.Luo, H.Y. Wang, X.J.Chen, Y.M.Luo, Z.Y.Wen, C.A.Chen, Z.Y.Huang, C.X.Liu, Y.F.Xiong, Y.Shi, Q.H.Lei, Z.W.Zhou, H.Xie, Y.W.Yang, Y.Q.Jing, J.J.Xiao, X.B.Jia. Design Description Document (DDD) for the Chinese Helium Cooled Solid Breeder (CH HCSB) Test Blanket Module (Version II) (Z). Oct. 20, 2005.
G.S. Zhang, Z.Q. Li, K.M. Feng, Z. Zhao. Investigation of Neutronics for China ITER TBM and CH DEMO Blanket with Helium-cooled Ceramics Breeding Concept, Dissertation for Ph.D. Fusion Engineering and Design (2007.7) (To be published).
G. S. Zhang, K.M. Feng, Z.Q. Li , Z. Chen, T.Yuan. Recent Neutronics Analysis and comparison for China ITER HCSB TBM, 21st IAEA Fusion Energy Conference, October 16-21,2006,Chengdu, China.
G.S. Zhang ,K.M. Feng,Z.Q. Li, Z. Chen, T. Yuan, Calculation of 3-D Neutronics for China HCSB TBM Module with 3x3 Sub-modules, Nuclear Physics Review, Vol. 23. No.2, Jun, 2006.
G.S. Zhang,K.M. Feng,Z. Chen,R.G. Chen,T. Yuan,Z.Q. Li Calculations of the 3-D Neutronics for CH HCSB TBM with 3x3 Sub-modules, Nuclear Fusion and Plasma Physics, Vol.26,No.3,Sept. 2006.
G.S. Zhang, K.M. Feng,T. Yuan, Z. Chen. Neutronics Analysis for CH HCSB TBM, Nuclear Fusion and Plasma Physics, Vol.25,No.2,Sept. 2005. P.93-98
K.M. Feng, C.H. Pan, G.S. Zhang etc. Preliminary Design for China ITER Test Blanket Module [J], 21st IAEA Fusion Energy Conference.October 16-21,2006,Chengdu, China.
K.M. Feng, C.H. Pan, G.S. Zhang etc. Preliminary Design for China ITER Test Blanket Module [J], Nucl. Eng. Design, 2005.
K.M. Feng, G.S. Zhang, X.Y. Wang, G. Hu, T. Yuan, Preliminary Design for an ITER Test Blanket Module, Nuclear Physics Review,Vol.23, No.2, Jun.,2006.
G.S. Zhang, Z. Chen, T. Yuan. Neutronics Design of Chinese Helium-cooled Solid Blanket (HCSB)Test Blanket Module[A]. Symposium on the first Numerical Calculation & Materials [C](2004). Huangshan, Anhui, China.
Z. Chen, K.M. Feng, G.S. Zhang, T. Yuan, X.Y. Wang, Z. Zhao. Calculation and Analysis of Environment safety for ITER HCSB TBM, Nuclear Fusion and Plasma Physics, Vol. 25, No.3, 183-188, September, 2005.
Z.Q. Li, K.M. Feng, G.S. Zhang, T. Yuan. Optimization of tritium production for China ITER HCSB TBM, Nuclear Fusion and Plasma Physics, Vol.21, No.5, Sept.2005.
K.M. Feng and G.S. Zhang,“Tansmutation of transuranic actinides in a spherical torus tokamak fusion reactor” Nuclear Fusion 43(2003) Page 756-760
K.M. Feng, G. S. Zhang, M.G. Deng.“Transmutation of minor actinides in a spherical torus tokamak fusion reactor, FDTR”, Fusion Engineering and Design 63-64 (2002) 127-132.
G.S. Zhang, J.H. Huang, Z.Y.Xie.“Three-Dimensional Neutronics Design and Calculation for FEB-E”Proceedings of the Fifth China-Japan Symposium on Materials for Advanced Energy Systems and Fission & Fusion Engineering, pp.262-265. November 2-6,1998, Xi’an, China.
G.S. Zhang, J.H. Huang, P.Z.Deng, J.Wang,“Three-Dimensional Neutronics Shielding Analysis and Calculation for Engineering Design of Fusion Experimental Breeder”, Chinese Physics Letter, Proc. APFA & APPTC 42-44(ISSN 0256-307X), September,1998
G.S. Zhang, G.Z.Sheng, G. Hu. Study of system parameters and economics for a pulsed slender tokamak fusion reactor, Nuclear Fusion and Plasma Physics, Vol.19,No.3,P.134-140. Sep 1999.
G.S. Zhang, K.M. Feng Z.J.Guo. Study of Effect of Neutron Irradiation of Center-post for ST-based Transmutation reactor, Nuclear Fusion and Plasma Physics, Vol.22, No.1, P.25-29. March 2002.
X.Y. Wang, G.S. Zhang, Calculation of Keff and optimized parameters for China accelerator-driven system, Nuclear Fusion and Plasma Physics, Vol. 24, No. 2. 123-128. Jun, 2004.
G.S. Zhang, A.P. Sun. 3-D simulation of electric-magnetic field of slow wave system of TWT with millimeter wave, Chinese Nuclear Science and Technology, CNIC-01691, SWIP-0161. July, 2002.
B.Q.Deng, G.S. Zhang, M.Wang, P.Z. Deng. Inventory and recycle of tritium for fusion experimental breeder (FEB), Nuclear Fusion and Plasma Physics, Vol.18,No.2,P.18-24.June 1998
K.M. Feng, G.S. Zhang, Z.J.Guo. Neutronics Design for ST-based Transmutation reactor, Nuclear Fusion and Plasma Physics, Vol.21, No.1,P.13-20. March 2001
H.Yang, G.S. Zhang, A.P. Sun, X.D. Peng, J.Y. Cao. Numerical simulation of slow wave structure with coupled chamber for TWT, Nuclear Fusion and Plasma Physics. Vol. 24, No. 1, P.53-57, March 2004.
J.H. Huang, G.S. Zhang, Y.X.Yang. A Computational tool of neutronics for a fast thermal-coupled core system of ADS by adopting deterministic theory, Atomic Energy Science and Technology, Vol.40, No.2, 186-188, Mar, 2006.
J.H. Huang, Z.Y.Xie, G.S. Zhang. Application of new evaluated nuclear data library to design of the blanket for fusion-fission hybrid reactor, Computer Application in Nuclear Field, Vol. No.2, 93-97. 1997.
J.H. Huang, G.Z. Sheng, K.M. Feng, H.W. Shi, S.L. Xue, Z.Y. Xie, B.Q. Deng, T.Y. Yu, X.B. Zhou, G.S. Zhang, X.R. Wang, H. Zhang, G.P. Zhang, P.Zi Deng, G. Hu, J. Wang, T.J. Huo, J.L. Liu, X.L. Nu. Detailed Conceptual Design for Fusion-fission Experimental Hybrid Reactor, Internal report in SWIP, Mar, 1996.
G.S. Zhang. Development of simplified system code for a tokamak fusion-fission hybrid reactor - SYSTOK, Dissertation for Master Degree, 1993.
J.H. Huang, G.Z. Sheng, K.M. Feng, H.W. Shi, B. Zhang, Z.Y. Xie, B.Q. Deng, X.R. Wang, G.S. Zhang, T.J. Huo. Conceptual Design for Tokamak fusion-fission Engineering Test Breeder, Internal report in SWIP, Mar, 1990.