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1775篇 您的检索式：期刊名="Fusion Engineering Design"

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	题名	作者	年代	出处	被引量
1	Application of the Distributed Database (Data-Free-Way) ou the Analysis of Mechanical Properties in Neutron lrradiated 316 Stainless Steel 显示文摘	Fujita M Kinugawa J Tsuji H	2000	Fusion Engineering and Design2000，，5152：	2
2	European development of prototypes for ITER high heat flux components 显示文摘	Vieider G Merola M Anselmi F	2000	Fusion Engineering and Design2000，4950，：	2
3	Design study of the JT-60SA supervisory control system 显示文摘	Kawamata Y Naito O Kiyono K	2008	Fusion Engineering and Design2008，11，9：	1
4	Structure stability and self-healing capability of Er2O3 in situ coating on V-4Cr4Ti in liquid lithium显示文摘	Yao Z Y Suzuki A	2006	Fusion Engineering and Design2006，81，：	1
5	Application of PLC to dynamic control system for liquid He cryogenic pumping facility on JT-60U NBI system显示文摘	IKEDA Y	2008	Fusion Engineering and Design2008，83，23：	1
6	Preliminary design for a China ITER test blanket module 显示文摘	Feng K M Pan C H Zhang G S	2006	Fusion Engineering and Design2006，81，814：	1
7	Neutron Irradiation Effects on Optical Absorption of KU1 and KS-4V Quartz Glasses and Infrasi1301显示文摘	Leon M Marti n P Vila R	2009	Fusion Engineering and Design2009，84，71819110111：	1
8	Microstructure and property of SiC coating for carbon materials 显示文摘	Zhao Juan Wang Gui Guo Quangui	2007	Fusion Engineering and Design2007，82，：	1
9	Hot - dip A1uminiumDeposit as a Permeation Barrier for MANET Stee1 显示文摘	E Serra H G1asbrenner A Perujo	1998	Fusion Engineering and Design1998，41，：	1
10	Thermal response of plasma sprayed tungsten coating to high heat flux 显示文摘	Liu X Yang L Tamura S	2004	Fusion Engineering and Design2004，70，4：	1
11	An advanced computational algorithm for system analysis of tokamak power plants 显示文摘	Dragojlovic Z	2010	Fusion Engineering and Design2010，85，：	1
12	Search and retrieval method of similar plasma waveforms显示文摘	Nakanishi H Hochin T Kojima M	2004	Fusion Engineering and Design2004，71，14：	1
13	Pebble bed thermal mechanical theoretical model:Application at the geometry of test blanket module of ITER-FEAT nuclear fusion reactor显示文摘	Aquaro D Zaccari N	2005	Fusion Engineering and Design2005，75，：	1
14	Neutronic,thermal-hydraulic and stress analysis of RF lithium cooled test blanket module for ITER显示文摘	Vitkovsky I V Golovanov M M Divavin V A Kirillov I R Lipko A V Malkov A A Kartashev I A Komarov V M Ogorodnikov A P Schipakin O L	2000	Fusion Engineering and Design2000，4950，：	1
15	Conceptual design of the China fusion power plant FDS-II 显示文摘	WU Yican FDS TEAM	2008	Fusion Engineering and Design2008，83，1012：	1
16	Assessment of neutron irradiation effects on RAFM steels显示文摘	Ermile Gaganidze Jarir Aktaa	2012	Fusion Engineering and Design2012，，：	1
17	Nuclear analysis of DEMO water-cooled blanket based on sub-critical water condition 显示文摘	Liu C Tobita K Utoh H	2011	Fusion Engineering and Design2011，86，12：	1
18	Numerical analysis on thermal-hydraulic and dust transport behavior in fusion reactors at loss-of vacuum events 显示文摘	Takase K	2000	Fusion Engineering and Design2000，5152，：	1
19	A report on the first remote handling operations at JET 显示文摘	Rolfe A C Brown P Carte P	1999	Fusion Engineering and Design1999，46，24：	1
20	Lifus(lithium for fusion)6 loop design and construction显示文摘	Aiello A Tincani A Favuzza P	2013	Fusion Engineering and Design2013，88，76：	1

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