Elaboration and thermomechanical characterization of W/Cu functionally graded materials produced by Spark Plasma Sintering for plasma facing components

被引:25
作者
Autissier, E. [1 ]
Richou, M. [1 ]
Minier, L. [2 ]
Gardarein, J. -L. [3 ]
Bernard, F. [2 ]
机构
[1] CEA, IRFM, F-13108 St Paul Les Durance, France
[2] CNRS UB, UMR 6303, Lab Interdisciplinaire Carnot Bourgogne, F-21078 Dijon, France
[3] Aix Marseille Univ, IUSTI, UMR CNRS 7343, F-13453 Marseille, France
基金
欧盟地平线“2020”;
关键词
Functionally graded material; Spark plasma sintering; Thermal conductivity; Powder metallurgy; COOLED DIVERTOR;
D O I
10.1016/j.fusengdes.2015.05.066
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
The assembly of W block with a CuCrZr block has been produced by adding compliant W-Cu layers. Firstly, three W-Cu powders (W80Cu20, W60Cu40 and W40Cu60) were sintered by spark plasma sintering (SPS) to investigate the influences of sintering temperature and pressure on relative density and microstructure. The experimental results indicated that the relative density increases with temperature and Cu concentration, achieving a value of 94.1% for the W40Cu60 sample sintered at 1000 degrees C and a value of 83.1% for the W80Cu20 sample sintered at the same temperature. Then, a three-layer W-Cu assembly between a W block and a CuCrZr block was fabricated using similar sintering conditions to the W-Cu powders. The sintering temperature was limited at 1000 degrees C due to the CuCrZr melting temperature (1083 degrees C). The experimental results indicated that loading time, when the right sintering temperature and pressure are applied, is the most important parameter. (C) 2015 Elsevier B.V. All rights reserved.
引用
收藏
页码:1929 / 1932
页数:4
相关论文
共 18 条
[1]   Spark plasma sintering of pure and doped tungsten as plasma facing material [J].
Autissier, E. ;
Richou, M. ;
Minier, L. ;
Naimi, F. ;
Pintsuk, G. ;
Bernard, F. .
PHYSICA SCRIPTA, 2014, T159
[2]   Design optimization of plasma facing component with functional gradient material Cu/W interlayer [J].
Autissier, E. ;
Richou, M. ;
Bernard, F. ;
Missirlian, M. .
FUSION ENGINEERING AND DESIGN, 2013, 88 (9-10) :1714-1717
[3]   ITER EDA project status [J].
Chuyanov, VA .
JOURNAL OF NUCLEAR MATERIALS, 1996, 233 :4-8
[4]   Materials perspective - A survey of plasma facing materials for fusion power plants [J].
Cottrell, G. A. .
MATERIALS SCIENCE AND TECHNOLOGY, 2006, 22 (08) :869-880
[5]   Modular He-cooled divertor for power plant application [J].
Diegele, E ;
Krüssmann, R ;
Malang, S ;
Norajitra, P ;
Rizzi, G .
FUSION ENGINEERING AND DESIGN, 2003, 66-68 :383-387
[6]  
Garcia-Rosales C., 1994, NUCL MAT, V211, P202
[7]   Thermal-Diffusivity Measurement of Ceramic Coatings at High Temperature using "Front-Face" and "Rear-Face" Laser Flash Methods [J].
Hay, B. ;
Filtz, J. -R. ;
Hameury, J. ;
Davee, G. ;
Rongione, L. ;
Enouf, O. .
INTERNATIONAL JOURNAL OF THERMOPHYSICS, 2009, 30 (04) :1270-1282
[8]   Design and evaluation of an optimized W/Cu interlayer for W monoblock components [J].
Herrmann, Aurelia ;
Greuner, H. ;
Balden, M. ;
Bolt, H. .
FUSION ENGINEERING AND DESIGN, 2011, 86 (01) :27-32
[9]   Effect of heat treatments on the properties of CuCrZr alloys [J].
Ivanov, AD ;
Nikolaev, AK ;
Kalinin, GM ;
Rodin, ME .
JOURNAL OF NUCLEAR MATERIALS, 2002, 307 :673-676
[10]   Total pattern fitting for the combined size-strain-stress-texture determination in thin film diffraction [J].
Lutterotti, Luca .
NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION B-BEAM INTERACTIONS WITH MATERIALS AND ATOMS, 2010, 268 (3-4) :334-340