Effects of vanadium concentration on the densification, microstructures and mechanical properties of tungsten vanadium alloys

被引:66
作者
Arshad, Kameel [1 ]
Zhao, Ming-Yue [2 ]
Yuan, Yue [1 ]
Zhang, Ying [1 ]
Zhao, Zhen-Hua [1 ]
Wang, Bo [3 ]
Zhou, Zhang-Jian [2 ]
Lu, Guang-Hong [1 ]
机构
[1] Beihang Univ, Sch Phys & Nucl Energy Engn, Beijing 100191, Peoples R China
[2] Univ Sci & Technol Beijing, Sch Mat Sci & Engn, Beijing 100083, Peoples R China
[3] Beijing Univ Technol, Coll Mat Sci & Engn, Beijing 100124, Peoples R China
关键词
FUSION POWER-PLANT; IRRADIATED TUNGSTEN; RETENTION; COMPOSITES; COMPONENTS; RESISTANCE; TANTALUM; NEUTRON;
D O I
10.1016/j.jnucmat.2014.04.019
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Tungsten based vanadium alloys have been fabricated by powder metallurgy and consolidated by spark plasma sintering (SPS) at temperature of 1600 degrees C for 3-5 min at 50 MPa. Four different concentrations of vanadium ranging from 1 to 10 wt.% were used to investigate the behavior of the developed alloys. X-ray diffraction analyses were performed for all four compositions of tungsten vanadium alloys. The morphology of cross sectional crack surfaces of sintered alloys was analyzed by scanning electron microscopy. The variations of vanadium concentration has not only shown an obvious impact on the microstructures, but also improved the densification and mechanical properties of the tungsten based materials. The maximum relative density of 98.5% was achieved for the highest concentration (10 wt.%) of vanadium alloy with micro hardness of 507 HV and good bending strength of 692.5 MPa. (C) 2014 Elsevier B.V. All rights reserved.
引用
收藏
页码:96 / 100
页数:5
相关论文
共 23 条
[1]  
[Anonymous], RARE METAL MAT ENG
[2]   Hydrogen isotope retention and recycling in fusion reactor plasma-facing components [J].
Causey, RA .
JOURNAL OF NUCLEAR MATERIALS, 2002, 300 (2-3) :91-117
[3]   Overview of the vanadium alloy researches for fusion reactors [J].
Chen, J. M. ;
Chernov, V. M. ;
Kurtz, R. J. ;
Muroga, T. .
JOURNAL OF NUCLEAR MATERIALS, 2011, 417 (1-3) :289-294
[4]   Sigma phase formation in irradiated tungsten, tantalum and molybdenum in a fusion power plant [J].
Cottrell, GA .
JOURNAL OF NUCLEAR MATERIALS, 2004, 334 (2-3) :166-168
[5]   Retention and surface blistering of helium irradiated tungsten as a first wall material [J].
Gilliam, SB ;
Gidcumb, SM ;
Parikh, NR ;
Forsythe, DG ;
Patnaik, BK ;
Hunn, JD ;
Snead, LL ;
Lamaze, GP .
JOURNAL OF NUCLEAR MATERIALS, 2005, 347 (03) :289-297
[6]   Deuterium retention in rhenium-doped tungsten [J].
Golubeva, A. V. ;
Mayer, M. ;
Roth, J. ;
Kurnaev, V. A. ;
Ogorodnikova, O. V. .
JOURNAL OF NUCLEAR MATERIALS, 2007, 363 (893-897) :893-897
[7]   Hydrogen interaction with point defects in tungsten [J].
Heinola, K. ;
Ahlgren, T. ;
Nordlund, K. ;
Keinonen, J. .
PHYSICAL REVIEW B, 2010, 82 (09)
[8]   On the potential of tungsten-vanadium composites for high temperature application with wide-range thermal operation window [J].
Hobe, Joerg ;
Gumbsch, Peter .
JOURNAL OF NUCLEAR MATERIALS, 2010, 400 (03) :218-231
[9]   Development of ultra-fine grained W-(0.25-0.8)wt%TiC and its superior resistance to neutron and 3 MeV He-ion irradiations [J].
Kurishita, H. ;
Kobayashi, S. ;
Nakai, K. ;
Ogawa, T. ;
Hasegawa, A. ;
Abe, K. ;
Arakawa, H. ;
Matsuo, S. ;
Takida, T. ;
Takebe, K. ;
Kawai, M. ;
Yoshida, N. .
JOURNAL OF NUCLEAR MATERIALS, 2008, 377 (01) :34-40
[10]   Development of ultra-fine grained W-TiC and their mechanical properties for fusion applications [J].
Kurishita, H. ;
Amano, Y. ;
Kobayashi, S. ;
Nakai, K. ;
Arakawa, H. ;
Hiraoka, Y. ;
Takida, T. ;
Takebe, K. ;
Matsui, H. .
JOURNAL OF NUCLEAR MATERIALS, 2007, 367 :1453-1457