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		题名	作者	年代	出处	被引量
	1	High Heat Flux Testing of Plasma Facing Materials and Components Status and Perspectives for ITER Related Activities显示文摘	Linke J Escourbiac F Mazul F I	2007	Journal of Nuclear Materials2007，，：	1
	2	Testing of High Heat Flux Components Manufactured by ENEA for ITER Divertor显示文摘	Visca E Escourbiac F Libera S	2009	Fusion Engineering and Design2009，84，26：	1
	3	Experimental Acticity On The Definition Of Acceptance Criteria For The ITER Divertor Plasma Facing Components 显示文摘	Escourbiac F Constans S Vignal NV	2009	Fusion Engineering and Design2009，84，：	1
	4	High heat flux testing of plasma facing materials and components-Status and perspectives for ITER related activities 显示文摘	LINKE J ESCOURBIAC F MAZUL I V NYGREN R RODIG M SCHLOSSER J SUZUKI S	2007	Journal of Nuclear Materials2007，，：	1
	5	Development of an ultrasonic test method for the non-destructive examination of ITER divertor components显示文摘	ROCCELLA S CACCIOTTI E ESCOURBIAC F PIZZUTO A RICCARDI B TATI A VARONE P VISCA E	2009	Fusion Engineering and Design2009，84，711：	1
	6	J Nucl Mater显示文摘	Missirlian M Escourbiac F Merola M	2007	367-370:13302007，，：	1
	7	Activity of the European high heat flux test facility 显示文摘	Bobin-Vastra I Escourbiac F Merola M	2005	Fusion Engineering and Design2005，75，791：	1
	8	A mature industrial solution for ITER divertor plasma facing components 显示文摘	Escourbiac F Schlosser J Merola M	2005	Fusion Engineering and Design2005，7579，：	1
	9	Physics basis and design of the ITER plasma-facing components显示文摘	Pitts R A Carpentier S Escourbiac F Hirai T Komarov V Kukushkin A S Lisgo S Loarte A Merola M Mittear R Raffray A R Shimada M Stangeby P C	2011	Journal of Nuclear Materials2011，415，1：	1
	10	High heat flux components-readiness to proceed from near term fusion systems to power plants显示文摘	Raffray A R Nygren R Whyte D G Ahdel-Khalik S Doerner R Escourbiac F Evans T Goldston R J Hoe-Izer D T Konishi S Lorenzetto P Merola M Neu R Norajitra P Pitts R A Rieth M Roedig M Rognlien T Suzuki S Tillack M S' Wong C	2010	Fusion Engineering and Design2010，85，1：	1
	11	ITER tungsten divertordesign development and qualification program显示文摘	HIRAI T ESCOURBIAC F CARPENTIER-CHOUCHANA S	2013	Fusion Engineering and Design2013，88，9：	1
	12	Flat tile armour cooled by hypervapotron tube: a possible technology for ITER 显示文摘	Schlosser J Escourbiac F Merola M	2004	Physica Scripta2004，111，：	1
	13	Infrared characterization and high heat flux testing of plasma sprayed layers显示文摘	Chappuis Ph Escourbiac F Chantant M	2000	Journal of Nuclear Materials2000，，：	1
	14	Advanced qualification methodology for actively cooled plasma facing components显示文摘	DUROCHER A ESCOURBIAC F GROSMAN A	2007	Nucl Fusion2007，47，：	1
	15	ITER full tungsten divertor qualification program and progress显示文摘	HIRAI T ESCOURBIAC F CARPENTIER- CHOUCHANA S	2014	Phys Scr2014，159，：	1
	16	High heat flux testing of plasma facing materials and components-status and perspectives for ITER related activities显示文摘	LINKE J ESCOURBIAC F MAZUL I V	2007	Nucl Mater2007，，：	1

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