Properties of Ultrafine-Grained Tungsten Prepared by Ball Milling and Spark Plasma Sintering

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Tungsten is currently considered as the most suitable plasma facing material for the first wall of a nuclear fusion reactor. First wall will be subjected to harsh conditions that will gradually deteriorate properties of the wall material. Some studies point out that fine-grained tungsten could be more resistant to the structure and property changes than coarse-grained tungsten. However, tailoring of tungsten microstructure is very laborious. Due to its high melting point, tungsten is very often processed mechanically and subsequently sintered into a compact body. In this study, preparation of ultrafine-grained tungsten by mechanical processing in a planetary ball mill was examined. Three types of tungsten samples were compared. One was made from coarse grained tungsten powder consolidated by SPS (spark plasma sintering). Other two samples were prepared from the powder processed in a planetary ball mill with and without addition of Y2O3. After ball milling, the powders were consolidated by SPS, i.e. fast sintering process that allows preserving fine-grained structure of the powder material. Properties of the samples such as hardness and thermal conductivity were examined and correlated with the processing history and microstructure.

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399-404

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January 2016

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© 2016 Trans Tech Publications Ltd. All Rights Reserved

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[1] H. Bolt, A. Brendel, D. Levchuk, H. Greuner, H. Maier, Materials for the plasma-facing components of fusion reactors, J. Nucl. Mater. 329–333 (2004) 66–73.

DOI: 10.1179/174892406x144451

Google Scholar

[2] N. Yoshida, Review of recent works in development and evaluation of high-Z plasma facing materials, J. Nucl. Mater. 266-269 (1999) 197-206.

DOI: 10.1016/s0022-3115(98)00817-4

Google Scholar

[3] D. Nishijima, M.Y. Ye, N. Ohno, S. Takamura, Incident ion energy dependence of bubble formation on tungsten surface with low energy and high flux helium plasma irradiation, J. Nucl. Mater. 99 (2003) 313–316.

DOI: 10.1016/s0022-3115(02)01368-5

Google Scholar

[4] N. Yoshida, H. Iwakiri, K. Tokunaga, T. Baba, Impact of low energy helium irradiation on plasma facing metals, J. Nucl. Mater. 337 (2005) 946–950.

DOI: 10.1016/j.jnucmat.2004.10.162

Google Scholar

[5] M. Efe, O. El-Atwani, Y. Guo, D.R. Klenosky, Microstructure refinement of tungsten by surface deformation for irradiation damage resistance, Scripta Mater. 70 (2014) 31–34.

DOI: 10.1016/j.scriptamat.2013.08.013

Google Scholar

[6] M. Samaras, P.M. Derlet, H. Van Swygenhoven, M. Victoria, Radiation damage near grain boundaries, Philos. Mag. 83 (2003) 3599–3607.

DOI: 10.1080/14786430310001600222

Google Scholar

[7] S.C. Cifuentes M.A. Monge P. Pérez, On the oxidation mechanism of pure tungsten in the temperature range 600–800°C, Corros. Sci. 57 (2012) 114–121.

DOI: 10.1016/j.corsci.2011.12.027

Google Scholar

[8] A. Suslova, O. El-Atwani, D. Sagapuram, S. S. Harilal, A. Hassanein, Recrystallization and grain growth induced by ELMs-like transient heat loads in deformed tungsten samples, Sci. Rep. 4 (2014) 06845.

DOI: 10.1038/srep06845

Google Scholar

[9] O. El-Atwani, G. Sean, E. Mert, G. De Temmerman, T. Morgan, K. Bystrov, D. Klenosky, Q. Tian, J. P. Allain, Ultrafine Tungsten as a Plasma-Facing Component in Fusion Devices: Effect of High Flux, High Fluence Low Energy Helium Irradiation, Nucl. Fusion, 54 (2014).

DOI: 10.1088/0029-5515/54/8/083013

Google Scholar

[10] J. Tan, Z-J. Zhou, X-P. Zhu, S-Q. Guo, D-D. Qu, M-K. Lei, C-C. Ge, Evaluation of ultra-fine grained tungsten under transient high heat flux by high-intensity pulsed ion beam, T. Nonferr. Metal. Soc. 5 (2012) 1081−1085.

DOI: 10.1016/s1003-6326(11)61286-7

Google Scholar

[11] K. Youngmoo, H.L. Kyong, Eun-Pyo K., D-I. Cheong, S.H. Hung, Fabrication of high temperature oxides dispersion strengthened tungsten composites by spark plasma sintering process, Int. J. Refract. Met. H. 27 (2009) 842–846.

DOI: 10.1016/j.ijrmhm.2009.03.003

Google Scholar

[12] V. Barabash, G. Federici, R. Matera, A.R. Raffray, ITER Home Team, Armour Materials for the ITER Plasma Facing Components, Phys. Scr. 81 (1999) 74-83.

DOI: 10.1238/physica.topical.081a00074

Google Scholar

[13] F. Koch, S. Köppl, H. Bolt, Self passivating W-based alloys as plasma-facing material, J. Nucl. Mater. 386–388 (2009) 572–574.

DOI: 10.1016/j.jnucmat.2008.12.179

Google Scholar

[14] R. W. Cheary, A. Coelho, A fundamental parameters approach to X-ray line-profile fitting, J. Appl. Cryst. 2 (1992) 109-121.

DOI: 10.1107/s0021889891010804

Google Scholar

[15] L. Veleva, R. Schaeublin, M. Battabyal, T. Plociski, N. Baluc, Investigation of microstructure and mechanical properties of W–Y and W–Y2O3 materials fabricated by powder metallurgy method, Int. J. Refract. Met. H. 50 (2015) 210-216.

DOI: 10.1016/j.ijrmhm.2015.01.011

Google Scholar

[16] Z.M. Xie, R. Liu, S. Miao, T. Zhang, X.P. Wang, Q.F. Fang, C.S. Liu, G.N. Luo, Effect of high temperature swaging and annealing on the mechanical properties and thermal conductivity of W-Y2O3, J. Nucl. M. 464 (2015) 193-199.

DOI: 10.1016/j.jnucmat.2015.04.050

Google Scholar