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18篇 您的检索式：作者名="ANTIPENKOV"

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		题名	作者	年代	出处	被引量
	1	Design of a kJ-class HiLASE laser as a driver for inertial fusion energy显示文摘We present the results of performance modeling of a diode-pumped solid-state HiLASE laser designed for use in inertial fusion energy power plants. The main amplifier concept is based on a He-gas-cooled multi-slab architecture similar to that employed in Mercury laser system. Our modeling quantifies the reduction of thermally induced phase aberrations and average depolarization in Yb3+:YAG slabs by a combination of helium cryogenic cooling and properly designed(doping/width) cladding materials.	Antonio Lucianetti Magdalena Sawicka Ondrej Slezak Martin Divoky Jan Pilar Venkatesan Jambunathan Stefano Bonora Roman Antipenkov Tomas Mocek	2014	High Power Laser Science and Engineering2014，2，2：	2
	2	ITER Fuel Cycle R&D: Consequences for the Design显示文摘	GLUGLA M MURDOCH DK ANTIPENKOV A	2006	Fusion Eng Des2006，81，：	1
	3	The ITER tritium systems 显示文摘	GLUGLA M ANTIPENKOV A BELO- GLAZOV S	2007	Fusion Engineering and Design2007，82，：	1
	4	ITER Fuel Cycle R&D: Consequences for the Design显示文摘	Glugla M Murdoch D K Antipenkov A	2006	Fusion Eng Des2006，81，：	1
	5	The ITER tritium systems显示文摘	Glugla M Antipenkov A Beloglazov S		0，，5：	1
	6	ITER fuel cycle R&D: Consequences for the design 显示文摘	Glugla M Murdochb D K Antipenkov A	2006	Fusion Engineering and Design2006，81，：	1
	7	The ITER tritium systems显示文摘	Glugla M Antipenkov A Beloglazov S	2007	Fusion Engineering and Design2007，82，：	1
	8	Thermal lensing in high-power diode-pumped Yb : KGW laser显示文摘	D Stuinskas R Antipenkov A Varanavicius	2010	Lithuanian Journal of Physics2010，50，2：	1
	9	ITER fuel cycle R&D: Consequences for the design显示文摘	M. Glugla D.K. Murdoch A. Antipenkov S. Beloglazov I. Cristescu I.-R. Cristescu C. Day R. Laesser A. Mack	2005	Fusion Engineering and Design2005，，1：	1
	10	The ITER Tritium Systems显示文摘	Glugla M Antipenkov A Beloglazov S	2007	Fusion Eng Des2007，82，514：	1
	11	ITER glow discharge cleaning system显示文摘	Antipenkov A B Ladd P Marrs R	2001	Fusion Engineering and Design2001，，5657：	1
	12	The ITERTritium Systems显示文摘	Glugla M Antipenkov A Beloglazov S	2007	Fusion Engineering and Design2007，82，：	1
	13	Fusion-reactorblanket with Li17-Pb83 eutectic显示文摘	Antipenkov A Butko A Chepovski A	1991	Fusion Engineering andDesign1991，14，34：	1
	14	ITER Fuel Cycle R & D: Consequences for the De- sign显示文摘	Glugla M Murdoch D K Antipenkov A	2006	Fusion Eng Des2006，81，：	1
	15	ITER fuel cycle R&D:Consequences for the design显示文摘	GLUGLA M MURDOCH D K ANTIPENKOV A	2006	Fusion Engineering and Design2006，81，：	1
	16	The ITER tritium systems显示文摘	GLUGLA M ANTIPENKOV A BELO-GLAZOV S	2007	Fusion Engineering and Design2007，82，514：	1
	17	The ITER tritium systems显示文摘	Glugla M Antipenkov A Beloglazov S	2007	Fusion Engineering and Design2007，82，：	1
	18	Design of kJ-class HiLASE laser as a driver for inertial fusion energy——CORRIGENDUM显示文摘	Antonio Lucianetti Magdalena Sawicka Ondrej Slezak Martin Divoky Jan Pilar Venkatesan Jambunathan Stefano Bonora Roman Antipenkov Tomas Mocek	2014	High Power Laser Science and Engineering2014，2，3：	0

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