论文专著:
在国内外学术刊物《Fusion Engineering & Design》、《Nuclear Materials》、《Nuclear Fusion》、《Fusion Science and Technology》等发表论文160余篇。
发表中文期刊论文:
[1]石柯,朱昌达,张伟,王龙,冯勇进,杨远友,廖家莉,冯开明,刘宁,杨吉军.阻氚涂层辐照-渗氢耦合装置的设计(英文)[J].四川大学学报(自然科学版),2021,58(03):129-136.
[2]杨国平,廖洪彬,王晓宇,盛倩,张宽,冯勇进,冯开明.退火工艺对CLF-1低活化钢组织和力学性能的影响[J].材料热处理学报,2019,40(11):108-115.
[3]巩保平,冯勇进,余果,廖洪彬,王晓宇,冯开明.颗粒粒度对颗粒床有效热物性影响的实验研究[J].工程热物理学报,2019,40(05):1151-1159.
[4]胡志强,赵奉超,武兴华,廖洪彬,王晓宇,冯开明.聚变堆用CLF-1钢与316L钢TIG焊接接头组织与性能初步研究[J].核聚变与等离子体物理,2018,38(04):446-451.
[5]巩保平,冯勇进,何开辉,廖洪彬,王晓宇,冯开明.固态氚增殖包层中球床堆积性能研究[J].核聚变与等离子体物理,2018,38(04):420-427.
[6]胡志强,赵奉超,赵周,廖洪彬,武兴华,王晓宇,冯开明.低活化马氏体钢热等静压焊接接头性能初步研究[J].核聚变与等离子体物理,2018,38(03):344-349.
[7]杨国平,廖洪彬,冯勇进,王晓宇,冯开明.工业化生产CLF-1钢轧板力学性能差异研究[J].核聚变与等离子体物理,2018,38(03):362-367.
[8]赵奉超,冯开明,曹启祥,栗再新,张国书.中国超导聚变工程实验堆氦冷固态包层中子学设计分析[J].核聚变与等离子体物理,2018,38(02):184-191.
[9]赵奉超,冯开明,曹启祥,栗再新,张国书.铜导体CFETR氦冷固态包层及屏蔽中子学设计与分析[J].核聚变与等离子体物理,2018,38(01):48-54.
[10]曹启祥,赵奉超,武兴华,王晓宇,冯开明,Michael Loughlin.ITER氦冷固态增殖剂试验包层模块中子学设计与优化[J].核聚变与等离子体物理,2018,38(01):63-68.
[11]叶兴福,冯开明,王晓宇,栗再新,王艳灵,王小勇,王芬,颜永江.小型氦气实验回路的设计与建造[J].核聚变与等离子体物理,2017,37(04):465-468.
[12]曹启祥,赵奉超,武兴华,王晓宇,冯开明,Michael Loughlin.中国氦冷固态增殖剂试验包层模块系统活化计算分析[J].核聚变与等离子体物理,2017,37(02):167-172.
[13]巩保平,冯勇进,刘洋,廖洪彬,王晓宇,冯开明.HCCB-TBM包层Li_4SiO_4球床堆积结构的数值模拟[J].核聚变与等离子体物理,2017,37(02):173-180.
[14]王苏豪,曹启祥,武兴华,王晓宇,张国书,冯开明.HCCB-DEMO氦冷固态包层热工水力计算及分析[J].核聚变与等离子体物理,2017,37(01):58-63.
[15]王芬,冯开明,王晓宇,叶兴福,张国书.流动氦气出口温度控制仿真与分析[J].核聚变与等离子体物理,2016,36(02):154-159.
[16]缪鹏,王苏豪,张国书,冯开明.紧凑型托卡马克聚变实验堆包层设计及中子学分析[J].核聚变与等离子体物理,2015,35(04):327-333.
[17]缪鹏,赵奉超,曹启祥,张国书,冯开明.Preliminary Shielding Analysis for HCCB TBM Transport[J].Plasma Science and Technology,2015,17(09):781-786.
[18]曹启祥,赵奉超,赵周,武兴华,栗再新,王晓宇,冯开明.Neutronic Calculation Analysis for CN HCCB TBM-Set[J].Plasma Science and Technology,2015,17(07):607-611.
[19]王泽明,胡刚,陈路,陶海燕,陈高詹,叶兴福,王平怀,俞德怀,王世忠,李勇,冯开明.中国固态增殖剂实验包层小模块工程结构设计与研制工艺探讨[J].核聚变与等离子体物理,2015,35(02):125-130.
[20]胡刚,冯开明,赵周,张国书,王琦杰,曹启祥,王泽明,俞德怀,陶诗泉,王世忠,陶海燕.中国氦冷固态增殖剂试验包层模块改进设计与关键工艺研究[J].核聚变与等离子体物理,2014,34(04):314-319.
[21]汪卫华,程德胜,冯开明,邓海飞.中国HCCB-TBM氚增殖球床热工水力学特性数值模拟[J].核聚变与等离子体物理,2014,34(03):200-206.
[22]赵周,胡刚,王琦杰,曹启祥,张国书,冯开明.中国氦冷固态增殖剂试验包层模块1×4方案子模块后板结构设计[J].核聚变与等离子体物理,2014,34(03):224-229.
[23]王琦杰,曹启祥,赵周,冯开明.中国氦冷固态增殖剂试验包层模块第一壁的改进设计与分析[J].核聚变与等离子体物理,2014,34(03):230-234.
[24]朱正和,罗德礼,冯开明.核磁矩的磁性热力学函数的统计热力学计算[J].核聚变与等离子体物理,2013,33(03):200-205.
[25]王杰,苏光辉,田文喜,秋穗正,向斌,张国书,冯开明.基于RELAP5的中国氦冷固态包层真空室外破口瞬态特性分析[J].原子能科学技术,2013,47(06):926-932.
[26]冯勇进,冯开明,曹启祥,张建利,胡劲.Current Status of the Fabrication of Li_4SiO_4and Beryllium Pebbles for CN HCCB TBM in SWIP[J].Plasma Science and Technology,2013,15(03):291-294.
[27]陈颜静,冯开明,张国书,栗再新.主破裂事故下中国固态实验包层模块电磁场分析[J].核聚变与等离子体物理,2012,32(04):338-343.
[28]张明春,冯开明,栗再新,赵奉超.聚变-裂变混合堆三种嬗变包层中子学方案初步分析[J].核聚变与等离子体物理,2012,32(04):344-350.
[29]赵周,陈茂爱,王平怀,冯开明,张国书.中国固态包层模块单轴热扩散焊接实验初步研究[J].核聚变与等离子体物理,2012,32(01):51-55.
[30]叶兴福,冯开明,罗天勇,张国书.ITER TBM第一壁制造方法与样件试制[J].核聚变与等离子体物理,2011,31(04):356-359.
[31]赵奉超,栗再新,张国书,冯开明,曹启祥.中国氦冷固态TBM对ITER环向场线圈能量沉积的影响[J].核聚变与等离子体物理,2011,31(04):360-364.
[32]武兴华,赵奉超,赵周,栗再新,张国书,冯开明.HCSB-DEMO包层热工水力及中子学计算[J].核聚变与等离子体物理,2011,31(03):235-240.
[33]郑国尧,冯开明,盛光昭,潘宇东,何宏达.Comparative Study of the SN, DDN and DN Diverter Plasma Simulations for HCSB-DEMO[J].Plasma Science and Technology,2011,13(01):26-29.
[34]张国书,冯开明.中国HCSB TBM模块的优化与设计进展[J].核动力工程,2010,31(S2):107-110.
[35]郑国尧,冯开明,盛光昭,潘宇东,何宏达.Simulation of Boundary Plasma for HCSB-DEMO by Using 2D Edge Plasma Transport Code SOLPS5.0[J].Plasma Science and Technology,2010,12(02):139-143.
[36]向斌,冯开明,叶兴福,秋穗正.中国氦冷固态实验包层氦气实验回路设计分析[J].核聚变与等离子体物理,2010,30(01):71-75.
[37]栗再新,冯开明,张国书,郑国尧,赵奉超.氦气、水和熔盐冷却的混合堆中子学性能研究[J].原子能科学技术,2009,43(S2):223-226.
[38]赵周,冯开明,张国书,袁涛.中国ITER固态增殖剂实验包层模块第一壁瞬态热分析[J].核聚变与等离子体物理,2009,29(04):348-352.
[39]赵周,冯开明,张国书,袁涛.中国ITER固态实验包层模块热工水力优化设计和分析[J].核科学与工程,2009,29(04):299-307.
[40]郑国尧,冯开明,盛光昭.Simulation of Plasma Parameters for HCSB-DEMO by a 1.5D Plasma Transport Code[J].Plasma Science and Technology,2009,11(06):651-656.
[41]赵周,冯开明,张国书,袁涛.中国ITER固态实验包层模块第一壁结构初步分析[J].核聚变与等离子体物理,2009,29(03):258-263.
[42]冯开明.可控核聚变与国际热核实验堆(ITER)计划[J].中国核电,2009,2(03):212-219.
[43]袁涛,冯开明,李增强,赵周.中国氦冷却固态增殖剂实验包层热工设计[J].核聚变与等离子体物理,2009,29(02):152-155.
[44]马丽华,冯开明,叶兴福,陈焕新.高温氦气实验回路氢气主冷却回路的概念设计[J].核动力工程,2009,30(02):62-64+74.
[45]李增强,冯开明,张国书,袁涛.中国氦冷固态实验包层2×6模型三维中子学计算[J].核聚变与等离子体物理,2009,29(01):59-61.
[46]曹启祥,冯开明,张国书.ITER固态试验包层模块设计三维活化分析[J].核聚变与等离子体物理,2009,29(01):62-66.
[47]郝腾飞,冯开明,赵周,袁涛.TBM子模块冷却剂流量分析及结构改进设计[J].核聚变与等离子体物理,2008(03):213-217.
[48]王琦杰,冯开明,陈志.中国ITER固态实验包层模块活化计算分析[J].核聚变与等离子体物理,2008(03):223-227.
[49]陈颜静,冯开明,高椿明,盛光召,张国书,秋穗正.中国ITER氦冷固态实验包层模块电磁安全分析[J].核聚变与等离子体物理,2008(03):228-232.
[50]袁涛,冯开明,王晓宇,陈志.中国ITER固态试验包层模块第一壁结构优化[J].核聚变与等离子体物理,2007(04):311-314.
[51]贾小波,杨永伟,周志伟,经荥清,冯开明.聚变堆混和球床包层中子学和热工水力特性研究[J].原子能科学技术,2007(05):565-569.
[52]郑国尧,冯开明.HCSB-DEMO等离子体参数的确定与初步分析[J].核聚变与等离子体物理,2007(03):212-216.
[53]杨进蔚,冯开明,程志.Preliminary Design of Neutron Flux and Spectrum Diagnostics in NT-TBM[J].Plasma Science and Technology,2007,9(02):219-222.
[54]邓柏权,黄锦华,冯开明,陈志,袁涛.SWITRIM程序的研制和使用概况[J].核聚变与等离子体物理,2006(04):314-317.
[55]冯开明.可控核聚变与ITER计划[J].现代电力,2006(05):82-88.
[56]贾小波,杨永伟,周志伟,经荥清,冯开明,张国书.ITER中国固态TBM中子倍增剂和氚增殖剂布置优化[J].清华大学学报(自然科学版),2006(09):1629-1632.
[57]冯开明.ITER实验包层计划综述[J].核聚变与等离子体物理,2006(03):161-169.
[58]杨进蔚,冯开明,陈志,杨青巍.产氚包层中聚变中子诊断系统的概念设计和计算[J].核聚变与等离子体物理,2006(03):190-194.
[59]袁涛,冯开明,王晓宇,陈志.ITER氦冷固体氚增殖剂实验包层模块结构设计[J].核聚变与等离子体物理,2006(03):195-200.
[60]李增强,冯开明,张国书,袁涛.中国氦冷固态增殖剂试验包层模块中子学计算[J].核聚变与等离子体物理,2006(03):201-204.
[61]高椿明,陈志,冯开明,王亚非.中国ITER实验包层模块电磁安全分析初步[J].核聚变与等离子体物理,2006(03):205-209.
[62]陈晓军,王和义,罗阳明,冯开明,温兆银.CH HCSB TBM中固体氚陶瓷增殖剂微球研究进展[J].核聚变与等离子体物理,2006(03):210-216.
[63]周志伟,解衡,杨永伟,经荥清,肖建军,贾小波,冯开明,陈志.中国ITER HCSB TBM冷却剂丧失事故分析[J].核聚变与等离子体物理,2006(03):223-227.
[64]杨进蔚,冯开明,陈志,杨青巍.ITER产氚试验包层模块中子诊断系统的初步设计[J].核聚变与等离子体物理,2006(03):228-232.
[65]李增强,冯开明,张国书.ITER HCSB TBM一维中子学优化设计[J].核聚变与等离子体物理,2006(03):233-238.
[66]冯开明,张国书,王晓宇,胡刚,袁涛,陈志,栗再新,赵周,李增强.ITER实验包层模块初步设计(英文)[J].原子核物理评论,2006(02):96-100.
[67]张国书,冯开明,李增强,陈志,袁涛.具有3×3子模块结构的中国HCSB TBM的三维中子学计算(英文)[J].原子核物理评论,2006(02):119-122.
[68]陈志,邓柏权,冯开明.先进燃料聚变反应性增强的新机制[J].物理学报,2006(04):1724-1730.
[69]李增强,冯开明,张国书,赵周.中国氦冷固态试验增殖模块(CH HCSB BT-TBM)产氚优化[J].科学技术与工程,2005(21):1599-1603.
[70]陈志,冯开明,张国书,袁涛,王晓宇,赵周.ITER试验包层模块活化计算与环境安全分析[J].核聚变与等离子体物理,2005(03):183-188.
[71]赵周,邓柏权,冯开明,陈志,袁涛,李增强.惯性约束核聚变的燃耗与增益[J].科学技术与工程,2005(17):1292-1293+1305.
[72]邓柏权,冯开明.D-~3He先进燃料靶惯性约束聚变的燃耗和增益[J].核聚变与等离子体物理,2005(02):87-92.
[73]张国书,冯开明,袁涛,陈志.ITER试验包层模块的中子学分析与设计[J].核聚变与等离子体物理,2005(02):93-98.
[74]陈志,冯开明,邓柏权,袁涛.D-~3He先进燃料聚变空间核动力推进器的可行性探索[J].科学技术与工程,2005(02):124-127.
[75]朱毓坤,黄锦华,王晓宇,冯开明.BFEB包层氦冷屏的结构力学分析与优化[J].核聚变与等离子体物理,2004(04):297-303.
[76]王晓宇,冯开明,黄锦华,张国书.使用MCNP程序调整和优化启明星实验装置设计方案[J].中国核科技报告,2004(02):4-10.
[77]陈志,冯开明,邓柏权,黄锦华.氘饱和状态下的液态锂表面的溅射问题[J].科学技术与工程,2004(08):672-673+678.
[78]陈志,冯开明.核聚变与开发月球~3He资源的可行性研究[J].科学技术与工程,2004(08):717-721.
[79]王晓宇,冯开明,黄锦华,张国书.启明星实验装置设计方案中K_(eff)与最优化参数的计算[J].核聚变与等离子体物理,2004(02):123-128.
[80]何开辉,黄锦华,冯开明.球环型产氚聚变堆中子学分析[J].核聚变与等离子体物理,2004(02):152-156.
[81]栗再新,冯开明.Flibe嬗变包层的概念设计研究[J].中国核科技报告,2003(03):23-31.
[82]邓梅根,冯开明.球形托卡马克堆嬗变中子学计算的比较研究[J].核聚变与等离子体物理,2003(01):7-12.
[83]冯开明,高椿明,何开辉.丝阵Z箍缩等离子体内爆过程单丝特性研究[J].核聚变与等离子体物理,2003(01):20-24.
[84]冯开明,张国书,邓梅根.嬗变少额锕系核废物MA的聚变堆中子学设计[J].中国核科技报告,2002(00):354-365.
[85]何开辉,黄锦华,冯开明.氚生产综述[J].中国核科技报告,2002(00):784-795.
[86]何开辉,潘传红,冯开明.托卡马克等离子体大破裂及防治综述[J].中国核科技报告,2002(00):797-809.
[87]邓梅根,冯开明,杨邦朝.球形环托卡马克堆嬗变中子学设计[J].中国核科技报告,2002(00):828-842.
[88]张国书,冯开明,郭增基.ST嬗变堆中心柱的中子学及中子辐照效应研究[J].核聚变与等离子体物理,2002(01):25-30.
[89]邓柏权,严建成,冯开明.小球形托卡马克嬗变堆堆芯参数分析[J].核科学与工程,2002(01):79-84.
[90]冯开明, swip.ac.cn,高椿明.丝阵Z-pinch等离子体内爆过程单丝特性研究[J].科学技术与工程,2002(01):55-58.
[91]黄锦华,冯开明,阳彦鑫,张国书,霍铁军.IAEA中子学(stage-1)基准的计算(二维离散坐标方法)[J].中国核科技报告,2001(00):50-63.
[92]冯开明,张国书,郭增基.球形托卡马克聚变嬗变堆中子学设计[J].核聚变与等离子体物理,2001(01):13-20.
[93]何开辉,冯开明,李强,高椿明.金属丝阵列Z箍缩装置中的瑞利-泰勒不稳定性[J].核聚变与等离子体物理,2000(04):241-245.
[94]朱毓坤,周小兵,黄锦华,冯开明,邓培智,霍铁军.FEB-E动态气靶偏滤器的研究[J].核聚变与等离子体物理,2000(02):73-80.
[95]朱毓坤,周小兵,黄锦华,冯开明,邓培智,霍铁军.FEB-E脱靶等离子体偏滤器的数值模拟[J].核聚变与等离子体物理,2000(01):10-14.
[96]冯开明.聚变实验增殖堆FEB-E放射性废物处置指标的计算[J].核聚变与等离子体物理,2000(01):15-22.
[97]朱毓坤,黄锦华,冯开明,邓培智,李毅强.聚变实验增殖堆FEB-E粒子抽除和抽气系统(英文)[J].核聚变与等离子体物理,1999(04):226-230.
[98]朱毓坤,周小兵,黄锦华,冯开明,邓培智,霍铁军.FEB混合堆偏滤器的物理研究[J].中国核科技报告,1999(00):928-944.
[99]冯开明,黄锦华,朱毓坤,邓培智,周小兵,王岷,霍铁军.FEB实验混合堆偏滤器工程结构与热工分析[J].中国核科技报告,1999(00):1063-1075.
[100]冯开明,胡刚.实验混合堆FEB设计的远距离维修指标计算[J].核聚变与等离子体物理,1999(01):29-34.
[101]冯开明,胡刚.托卡马克实验混合堆 FEB 嬗变 MA 可行性研究[J].核科学与工程,1998(04):44-51.
[102]周小兵,盛光昭,冯开明,朱毓坤,何开辉,龚学余.腐蚀和沉积对偏滤器靶板寿命的影响[J].核聚变与等离子体物理,1998(04):17-22.
[103]冯开明.实验混合堆FEB设计放射性计算与环境安全分析[J].中国核科技报告,1996(S1):83-84.
[104]冯开明.实验混合堆FEB设计放射性计算与环境安全分析(英文)[J].中国核科技报告,1996(00):661-673.
[105]冯开明,黄锦华,盛光昭.托卡马克商用混合堆堆内燃料循环优化设计[J].核科学与工程,1995(02):149-157.
[106]冯开明,黄锦华.在聚变堆中嬗变~(237)Np的研究[J].核科学与工程,1995(01):50-57.
[107]冯开明,邓柏权.D-~3He聚变堆MOONCITY的放射性及核废物处置问题[J].核科学与工程,1993(02):164-172+7.
[108]冯开明,阳彦鑫,黄锦华.混合堆放射性计算与FDKR程序研制[J].计算物理,1992(S1):582.
[109]冯开明.聚变堆第一壁辐照效应研究[J].核科学与工程,1991(04):318-324+5.
[110]冯开明,阳彦鑫.AF—DCDLIB:活化产物、裂变产物和锕系元素衰变链数据库[J].核科学与工程,1991(03):288-289+279+256.
[111]冯开明,谢中友.托卡马克商用混合堆燃耗计算[J].核科学与工程,1991(02):104-109+4.
[112]冯开明,谢中友.托卡马克商用混合堆燃耗计算[J].中国核科技报告,1990(S4):66-67.
[113]黄锦华,盛光昭,施汉文,游承伦,谢中友,邓柏权,冯开明,王学人,薛淑兰,王庆明,黄中琪,张飚,阳彦鑫,吴灵桥,张丽,张国书,吕晓兰,霍铁军.托卡马克工程试验混合堆概念设计[J].核聚变与等离子体物理,1990(04):193-208.
[114]冯开明,谢中友.托卡马克商用混合堆燃耗计算[J].中国核科技报告,1990(00):405-411.
[115]冯开明.聚变堆第一壁材料的活化特性研究[J].核科学与工程,1990(01):67-71+5.
发表中文会议论文:
[1]王龙,罗晓芳,王佳恒,杨吉军,冯勇进,廖家莉,杨远友,冯开明,刘宁,龚敏. MOD法制备Al_2O_3阻氚涂层及其表征[C]. 中国核科学技术进展报告(第五卷)——中国核学会2017年学术年会论文集第5册(核材料分卷、辐射防护分卷). 2017:150-155.
[2]巩保平,冯勇进,廖洪彬,王晓宇,冯开明. 基于离散元方法的氚增殖包层球床堆积结构的研究[C]. 中国核科学技术进展报告(第五卷)——中国核学会2017年学术年会论文集第7册(计算物理分卷、核物理分卷、粒子加速器分卷、核聚变与等离子体物理分卷、脉冲功率技术及其应用分卷、核工程力学分卷). 2017:136-143.
[3]王龙,杨吉军,冯勇进,廖家莉,杨远友,冯开明,刘宁. 金属有机物分解法(MOD)制备Al_2O_3阻氚涂层及其表征[C]. 第二届中国氚科学与技术学术交流会论文集. 2017:81.
[4]巩保平,冯勇进,廖洪彬,王晓宇,冯开明. 固态氚增殖包层中球床堆积性能实验和模拟研究[C]. 第二届中国氚科学与技术学术交流会论文集. 2017:38-40.
[5]张龙,王俊,王晓宇,冯开明. 中国ITER氦冷固体实验包层系统氚平衡参数性研究[C]. 第二届中国氚科学与技术学术交流会论文集. 2017:55.
[6]冯开明,王晓宇,张国书,栗再新,陈颜静,冯勇进. 中国ITER TBM改进设计与R&D新进展[C]. .2013核工业西南物理研究院年报.:中国核学会,2014:111-113.
[7]冯勇进,冯开明,刘洋,张建利,胡劲. 中国ITER TBM功能材料进展[C]. 2013核工业西南物理研究院年报. 2014:114-116.
[8]王泽明,胡刚,陈路,陶海燕,陈高詹,叶兴福,王平怀,俞德怀,冯开明,王世忠,李勇. 中国固态增殖剂实验包层小模块工程结构设计与研制工艺探讨[C]. 中国核学会.中国核科学技术进展报告(第三卷)——中国核学会2013年学术年会论文集第7册(核电子学与核探测技术分卷、脉冲功率技术及其应用分卷、核聚变与等离子体物理分卷). 2013:478-484.
[9]冯勇进,冯开明,张建利. 中子倍增材料铍小球的REP制备工艺研究[C]. 中国核科学技术进展报告(第二卷)——中国核学会2011年学术年会论文集第7册(核电子学与核探测技术分卷、脉冲功率技术及其应用分卷、核聚变与等离子体物理分卷). 2011:355-360.
[10]郑国尧,冯开明,孙爱萍. 示范聚变堆的等离子体参数模拟[C]. 第十五届全国等离子体科学技术会议会议摘要集. 2011:250.
[11]张国书,赵周,冯开明. 一种新的ITER氦冷固态TBM模块的概念设计[C]. 第四届全国反应堆物理与核材料学术研讨会论文集. 2009:16.
[12]冯勇进,冯开明,罗天勇. 正硅酸锂陶瓷粉末的合成[C]. 中国核科学技术进展报告——中国核学会2009年学术年会论文集(第一卷·第7册). 2009:474-478.
[13]陈颜静,冯开明,高椿明. 有效降低ITER环向磁场波纹度效应的初步研究[C]. 第十四届全国等离子体科学技术会议暨第五届中国电推进技术学术研讨会会议摘要集. 2009:153.
[14]张国书,冯开明,栗再新,李增强,陈志,曹启祥,王奇杰,赵奉超. 中国ITER氦冷固态试验包层模块(HCSB TBM)设计组中子学研究进展[C]. 第十二届反应堆数值计算与粒子输运学术会议论文集. 2008:360.
[15]李增强,冯开明,张国书,袁涛. ITER中国氦冷固态氚增殖剂包层中子学设计[C]. 第三届反应堆物理与核材料学术研讨会论文集. 2007:16.
[16]张国书,李增强,冯开明,赵周,袁涛. 具有氦冷固态氚增殖包层的中国DEMO聚变堆三维中子学研究[C]. 第三届反应堆物理与核材料学术研讨会论文集. 2007:17.
[17]刘海波,冯开明. 中国氦冷固态包层热工水力瞬态安全分析[C]. 第三届反应堆物理与核材料学术研讨会论文集. 2007:29.
[18]李增强,冯开明,张国书,袁涛. ITER中国氦冷固态氚增殖剂包层中子学设计[C]. 第三届反应堆物理与核材料学术研讨会论文摘要集. 2007:16.
[19]张国书,李增强,冯开明,赵周,袁涛. 具有氦冷固态氚增殖包层的中国DEMO聚变堆三维中子学研究[C]. 第三届反应堆物理与核材料学术研讨会论文摘要集. 2007:17.
[20]刘海波,冯开明. 中国氦冷固态包层热工水力瞬态安全分析[C]. 第三届反应堆物理与核材料学术研讨会论文摘要集. 2007:29.
[21]贾小波,杨永伟,周志伟,经荥清,冯开明. 聚变堆固态包层中子学分析[C]. 全国计算物理学会第六届年会和学术交流会论文摘要集. 2007:73.
[22]李增强,张国书,冯开明,袁涛. ITER中国氦冷固态氚增殖剂包层中子学设计[C]. 第十三届全国等离子体科学技术会议论文集. 2007:823.
[23]张国书,冯开明,李增强,袁涛. 基于氦冷固体增殖包层概念的中国DEMO堆的三维中子学研究[C]. 第十三届全国等离子体科学技术会议论文集. 2007:1183-1184.
[24]冯开明,张国书,王晓宇,袁涛,陈志,赵周,李增强. ITER HC-SB实验包层模块设计研究进展[C]. 第二届全国反应堆物理与核材料学术研讨会论文集. 2005:11.
[25]张国书,冯开明,袁涛,李增强,杨永伟,贾小波. 中国ITER氦冷固体试验包层(HCSB TBM)的最新的中子学分析与计算[C]. 第二届全国反应堆物理与核材料学术研讨会论文集. 2005:43.
[26]冯开明,黄锦华,张国书,胡刚,栗再新,王晓宇,袁涛,陈志. ITER HC-SB实验包层设计研究进展[C]. 第一届反应堆物理与核材料学术研讨会论文摘要集. 2004:30.
[27] 冯开明, 黄锦华, 阳彦鑫,“聚变--裂变混合堆放射性计算比较分析”,中国科协第二届青年学术年会四川卫星会议论文集, 西南交通大学出版社, 1995年8月。
发表英文会议论文:
[1]K.M. Feng,Y.X. Yang,Z.Y. Xie, "A Decay Chian Data Library for Activation Products, Fission Products and Actinides," distributed at US/PRC Workshop on FNT and Fusion Reactor Concepts, April 15, 1988, Tokyo, Japan.
[2]K.M. Feng, Y.X. Yang, "Radioactivity Calculation for a Tokamak Engineering Test Breeder,” Distributed at 2nd US/PRC Workshop on FNT and Fusion Reactor, Concepts, May14, 1989, Chengdu, P.R. China.
[3]J.H. Huang, K.M. Feng, et al., "Tokamak Breeder Conceptual Design," Distributed at 2nd US/PRC Workshop on FNT and Fusion Reactor Concepts, May 14, 1989, Chengdu, P.R. China.
[4]Y.X. Yang,K.M. Feng,"FDKR-A Radioactivity Calculation Code for Hybrid Reactor, "Distributed at 2nd US/PRC Workshop on FNT and Fusion Reactor Concepts, May 14, 1989, Chengdu, P.R. China.
[5]J.H. Huang, K.M. Feng, et al., "Conceptual Design of a Tokamak Commercial Breeder," Proc. of 13th Inter. Conf. on Plasma Phy. and Controlled Nucl. Fusion Research, Vol.3, 583(1990), IAEA- CN-53/G-2-6, IAEA, Vienna.
[6]K.M. Feng, "activation and Waste Disposal Aspects of Fusion Breeder," Proc. IEEE 14th Symp. on Fusion Eng., San Diego, Ca.(1991).
[7]J.H. Huang, K.M. Feng,...et al., "Preliminary Conceptual Design for a Tokamak Engineering Test Breeder," Proc. of 12th Inter. Conf. on Plasma Phy. and Controlled Nucl. Fusion Research, Vol.3, 309(1992) Nice ,France, IAEA-CN-03/G-I-3, IAEA, Vienna.
[8]J.H. Huang, K.M. Feng, et al., "Progress in Conceptual Design of a Tokamak Engineering Test Breeder," Pro. 3rd Annual Scientific Conf., RF Nuclear Society, MOSCOW (Sep.,1992).
[9]邓柏权, K.M. Feng等, “Feasibility Studies of D-3He Fusion Power in China,” Presented at the Third Sino-Japanese Symposium on Materials for Advanced Energy Systems and Fission and Fission Engineering, Oct, 1995, Chengdu, China.
[10]K.M. Feng,“Activation Calculation and Environment Safety Analysis for a Fusion Experimental Breeder FEB”, Presented at 4th Sino-Japanese Symposium on Materials for Advanced Energy Systems and Fission and Fission Engineering, July 26-29, 1996, 札幌,日本。.
[11]K.M. Feng, G.Hu,“Transmutation of Nuclear Wastes in a Fusion Breeder,” Present at International Symposium on Fusion Nuclear Technology, Aril 6-11,1997, Meiji Kinenkan, Tokyo, Japan.
[12]KM. Feng, G.Hu, "Management of Waste from the Fusion Experimental Breeder," Presented at the Third Sino-Japanese Symposium on Materials for Advanced Energy Systems and Fission and Fission Engineering, Nov.2-6., 1998, Xian, China.
[13]G.Hu, K.M. Feng, "FWLC-A Computer Program for Predicting the Lifetime of the Fusion Reactor Components," Presented at the Third Sino-Japanese Symposium on Materials for Advanced Energy Systems and Fission and Fission Engineering, Nov.2-6., 1998, Xian, China.
[14]K.M.Feng,G.S.Zhang, “Transmutation of Minor Actinides in a ST Tokamak Fusion Reactor,” Presented at the Sixth Sino-Japanese Symposium Materials for Advanced Energy Systems & Fission and Fusion Engineering, Dec.4-7, 2000, Kyushu University, Fukuoka, Japan
[15]Jinhua Huang, Kaiming Feng, “Overview of Fusion-Fission Hybrid Reactor Design Study in China”, J. of Fusion Science and Technology, Vol.42, July , (2002) 138-145.
[16]K.M.Feng, G.SH.Zhang, M.G.Deng, Transmutation of Minor Actinides in a Spherical Torus Tokamak Fusion Reactor, FDTR, Presented at the 6th International Symposium of Fusion Nuclear Technology (ISFENT-6), university of Califormia, 8-12 April, 2002.
[17]Feng Kaiming, Zhang Guoshu, Deng Meigen, Transmutation of minor actinides in a spherical torus tokamak fusion reactor, FDTR, Presented at the 19th IAEA Fusion Energy Conference, Oct.14-19, 2002, Lyon, France.
[18]K.M. Feng, Activation Calculation for a Fusion Experimental Breeder, FEB-E, Proceeding of the Seventh China--Japan Symposium Materials for Advanced Energy Systems & Fission and Fusion Engineering, World Scientific, p.64-71 (2003).
[19]J.H. Huang, K.M. Feng, C.H. Pan, “ITER TBM Design Concepts from CH Party”, presented at TBWG-11 meeting, Garching, Germany, Oct.22-24, 2003.
[20]K.M. Feng,J.H. Huang, C.H. Pan, “ITER TBM Design Concepts from CH Party”, presented at BWG-11 meeting, Garching, Germany, Oct.22-24, 2003.
[21]K.M.Feng, …..Z. Chen, et al., Fusion/transmutation reactor studies based on the spherical torus concept,IAEA 20th Fusion Energy Conference, Nov. 1-6, Portugal, 2004
[22]K.M. Feng, G.S. Zhang, G. Hu, ZH.X. Li, X.Y. Wang, T. Yuan, ZH.Chen, Preliminary Design for the HC-SB ITER Test Blanket Module in China, 8th Japan-China Symposium on Materials for Advanced Energy Systems and Fission & Fusion Engineering,Oct.4-8, 2004, Japan..
[23]K.M. Feng, J.H. Huang, B.Q. Deng, G.S. Zhang, G. Hu, Z.X. Li, X.Y. Wang, T. Yuan, Z.,Chen, Fusion/transmutation reactor studies based on the spherical tours concept, 20th IAEA Fusion Energy Conference,1-6 November 2004, Vilamoura, Portugal.
[24]Kaiming Feng*, Guoshu Zhang, Gang Hu, Zaixin Li Xiaoyu Wang, Tao Yuan, Zhi Chen,Design Studies For The Iter Test Blanket Module , With Helium-Cooled Solider Breeder (HC-SB) Concept, 13th International Conference on Nuclear Engineering, Beijing, China, May 16-20, 2005, (ICONE13- 50898)
[25]K.M. Feng, C.H. Pana, G.S. Zhanga, D. L. Luob, Z.W. Zhouc, H.Y. Wangb, Y.W. Yangc, X.Y. Wang,G. Hua, T. Yuana, Z. Chena, C.A.Chenb, Z.X. Lia, Z.Y. Wend, Z. Zhaoa, Z.Q. Lia, reliminary design for a China ITER test blanket module, 7th International sysposium on Fusion Nuclear Technology, May 22-27,2005, Japan.
[26] Feng Kaiming, “New Progress and R&D Plans of China Solid TBM Program”, Presented at TBWG-16 Meeting – Beijing, China, November 15-17, 2005.
[27] Feng Kaiming, “Progress and Status of China Solid TBM Program”, Presented at TBWG-17 Meeting – Cadarache, France, April 4-6, 2006,
[28]Feng Kaiming, “Activation Calculation for a Fusion-driven Sub-critical Experimental Breeder, FDEB”, Presented at 8th IAEA Technical Meeting on “Fusion Power Plant Safety”,10-13 July 2006, Vienna, Austria.
[29]Feng Kaiming, et al., ““Preliminary design of China ITER HC-SB TBM Program,” Presented at 3rd PRC/US MCF Collaboration workshop – Dalian, China, May 18-19, 2006
[30]K.M.Feng and HCSB-TBM Team, Design progress and R&D program of Chinese solid TBM, Presented at ITER-TBM TBWG-17meeting, Cardalache, France, April 5-7, 2006.
[31]K.M. Feng, C.H. Pan, G.S. Zhang, D. L. Luo, Z.W. Zhou, H.Y. Wang, X.Y. Wang, Z. Chen, T. Yuan, C.A. Chen, Z. Zhao, Z.Q. Li, C.M.Gao, G. Hu, G.Y. Zheng, Z.X. Li, Z. X.F. Ye, Progress and Status of ITER Solid Breeder Test Blanket Module in China, Presented at 14th International Workshop on Ceramic Breeder Blanket Interaction, Sep. 6-8, 2006, Petten, The Netherlands.
[32]K.M. Feng, Activation Calculation for a Fusion-driven Sub-critical Experimental Breeder, FDEB, Presented at 8th IAEA Technical Meeting on Fusion Power Plant Safety, 10–13 July 2006, IAEA Headquarters, Vienna, Austria.
[33]K.M. Feng, C.H. Pan, G.S. Zhang, X.Y. Wang, T.Yuan, Z. Chen, G. Hu, Z. Zhao, Z.Q. Li M. Gao, H.B. Liu, G.Y. Zheng,Preliminary Design of China ITER TBM with Helium-Cooled and Solid Breeder Concept,Presented at the 21st Fusion Energy Conference, Chengdu, China, 16-21 Oct. 2006.
[34]K.M. Feng, Activation Calculation for a Fusion-driven Sub-critical Experimental Breeder, FDEB, Presented at 8th IAEA Technical Meeting on Fusion Power Plant Safety, 10–13 July 2006, IAEA Headquarters, Vienna, Austria.
[35]K.M. Feng, C.H. Pan, G.S. Zhang, D. L. Luo, Z.W. Zhou, H.Y. Wang, X.Y. Wang, Z. Chen, T. Yuan, C.A. Chen, Z. Zhao, Z.Q. Li, C.M.Gao, G. Hu, G.Y. Zheng, Z.X. Li, Z. X.F. Ye, Progress and Status of ITER Solid Breeder Test Blanket Module in China, Presented at 14th International Workshop on Ceramic Breeder Blanket Interaction, Sep. 6-8, 2006, Petten, The Netherlands.
[36]K.M.Feng and HCSB-TBM Team, Design progress and R&D program of Chinese solid TBM, Presented at ITER-TBM TBWG-17meeting, Cardalache, France, April 5-7, 2006.
[37]K.M. Feng, Conceptual Design Study of Fusion DEMO Plant at SWIP, Presented at 2nd IAEA Technical Meeting on First Generation of Fusion Power Plant: Design & Technology, June 20-22, 2007, Vienna, Austria.
[38]K.M.Feng and HCSB-TBM Team, Progress and Status of CN HCSB TBM, Presented at ITER-TBM TBWG-18meeting, Cardalache, France, March 18-22, 2007.
[39]K.M.Feng, et al., Overview of China ITER solid breeder TBM design at SWIP, Presented at 8th International Symposium of Fusion Nuclear Technology (ISFNT-8), Sep.30-Oct.5, 2007, Heidelberg, Germany
[40]K.M. Feng, Z.Y. Xu, J.M. Chen, Overview of Fusion Reactor Design and Related Technology at SWIP, Presented at the 6th Asia Fusion Plama & Association (AFPA-207), Dec. 3-5, 2007, India.
[41]K.M. Feng, ITER-TBM Interface Input from China, 1st TBM-ITER Interface meeting, Cardalache, France, Nov..12-13, 2007.
[42]K.M. Feng, Overview of Design and R&D Status of Solid Breeder TBM in China, 4th US-PRC Magnetic Fusion Collaboration Workshop, May 5-8, 2008, Austin, Texas, USA.
[43]K.M. Feng, Overview of Design and R&D Status of Solid Breeder TBM in China, 2nd Japan- China Workshop on blanket and tritium technology, Sendai, Miyagi, Japan, May 9-10, 2008.
[44]K.M. Feng, Progress and Status of Design and R&D Status of Solid Breeder TBM in China, Presented at C-J Symposium on PWI and Fusion Technology, Oct.27-29, China, Huangshan,,2008。
[45]K K.M. Feng, C.H. Pan, G.S. Zhang, T. Yuan, Z. Chen, Z.Zhao, H.B. Liu, Z.Q. Li, G. Hu, X.Y. Wang, X.F. Ye, D.L. Luo, C.M. Gao, T.Y. LUO, Y.J. Feng, H.Y. Wang, Y.J. Chen, Z.W. Zhou,Z. X. Li, G.Y. Zheng, Overview of Design and R&D of solid breeder TBM in China, 22nd IAEA Fusion Energy Conference ,13-18 October 2008,Geneva, Switzerland.
[46]K.M. Feng, Study Activities of DEMO Plant at SWIP, Presented at 3nd IAEA Technical Meeting on First Generation of Fusion Power Plant: Design & Technology, 13-15, July 2009, Vienna, Austria.
[47]K.M. Feng, C.H. Pan, G.S. Zhang, T.Y. Luo, Z. Zhao, Y.J. Chen, Y.J. Feng, X.F. Ye, G. Hu, K.H. He, R.W. Niu, Z.X. Li, P.H. Wang, B. Xiang, L. Zhang, Q.J. Wang, F.C. Zhao, Q.X. Cao, F. Wang, T. Yan, G.Y. Zheng, Y. Liu, Y. Zhong, M.C. Zhang, and Chinese HCSB TBM team, Progress on Design and R&D for Helium-cooled Ceramic Breeder TBM China,Presented at 11th International Symposium on Fusion Nuclear Technology, Sptenmer,11-17,2011,Portland,US。
[48]K.M. Feng, G.S. Zhang, Z.X. Li, Z. Zhao, Y.J. Feng,Y.J. G. Hu, X.F. Ye, Y.J. Chen, P.H. Wang, B. Xiang, L. Zhang, Q.J. Wang, F.C. Zhao, Q.X. Cao, F. Wang, G.Y. Zheng, Y. Liu, Y. Zhong, M.C. Zhang, and Chinese HCSB TBM team, New Progress on Design and R&D for Helium-cooled Ceramic Breeder TBM China,Presented at 11th International Symposium on Fusion Nuclear Technology, 16-20 September 2013, Barcelona, Spain.