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	题名	作者	年代	出处	被引量
1	The reaction kinetics of lithium salt with water vapor 显示文摘	BALOOCH M DINH L N CALEF D F	2002	J NuclMater2002，303，：	1
2	The behaviour of control rod absorber under irra- diation显示文摘	BOURGOIN J COUVREUR F GOSSET D	1999	J NuclMater1999，275，：	1
3	Understanding the SOL Flow in L-Mode Plasma on Divertor Tokamaks, and Its Influence on the Plasma Transport 显示文摘	Asakura N	2007	NuclMater2007，，：	1
4	First-Principles Investigation on Dissolution and Diffusion of Oxygen in Tungsten显示文摘	Atkhamees A Liu Y L Lu G H	2009	NuclMater2009，393，：	1
5	Hydrogen Blister Formation and Cracking Behavior for Various Tungsten Materials 显示文摘	Ueda Y Funabiki T Shimada T	2005	NuclMater2005，，：	1
6	Behavior of Tungsten Exposed to High Fluencies of Low Energy Hydrogen Isotopes显示文摘	Venhaus T Causey R Doerner R	2001	NuclMater2001，290，293：	1
7	Erosion Simulation of First Wall Beryllium Armour under ITER Transient Heat Loads显示文摘	Bazylev B Janeschitz G Landman I	2009	NuclMater2009，，：	1
8	Self diffusion coefficient of lithium in lithiumoxide显示文摘	Oishi Y Kamel Y Akiyama M	1979	J NuclMater1979，87，23：	1
9	Fundamental aspects of defective nuclear fuel behavior and fission product release 显示文摘	LEWIS B J	1988	J NuclMater1988，160，：	1
10	Thermo-physical Properties of Uranium Dioxide显示文摘	Kink J F Chasanov M G Leibowitz L	1981	J NuclMater1981，102，：	1
11	Experi-mental and Thermodynamic Evaluation of the Melt-ing Behavior of Irradiated Oxide Fuels显示文摘	Adamson M G Aitken E A Caputi R W	1985	J NuclMater1985，130，：	1
12	New Scenarios of ICRF Wall Conditioning in TEXTOR and ASDEX Upgrade 显示文摘	Lyssoivan A Koch R Eester D Van	2007	NuclMater2007，，：	1
13	Optimization of Non-Oxidative Carbon-Removal Techniques by Nitrogen-Containing Plasmas显示文摘	Ferreira J A Tabares F L Tafalla D	2009	NuclMater2009，，：	1
14	Development of ferritic steels for reduced activation: The US program 显示文摘	Kluch R L Gelles D S Lechtenberg	1986	J NuclMater1986，14，：	1
15	Preparation and characterization of Al2O3/FexAly layers on manet steel 显示文摘	GLASBRENNER H BORGSTEDT H U	1994	J NuclMater1994，，：	1
16	Effects of dislocation on thermal helium de-sorption from iron and ferritic steel显示文摘	SUGANO R MORISHITA K IWAKIRI H etal	2002	J NuclMater2002，307，：	1
17	Design status and devel-opment strategy of China liquid lithium-lead blan-kets and related material technology显示文摘	WU Y C? FDS Team	2007	J NuclMater2007，，：	1
18	Hydrogenic retention in tungsten exposed to ITER divertor relevant plasma flux densities显示文摘	Wright G M Kleyn A W Alves E	2009	J NuclMater2009，，：	1
19	Binary effect of He and H on the intra-and inter-granular embrittlement in Fe显示文摘	Tian Z Xiao W Wan F	2010	J NuclMater2010，，3：	1
20	Long-term stability of TaC particles during tempering of 8%Cr-2&W steel显示文摘	TAMURA M SAKASEGAWA H	2007	J NuclMater2007，367，：	1

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