Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
권호 표지
DOI QR코드

DOI QR Code

Microstructure evolution and effect on deuterium retention in oxide dispersion strengthened tungsten during He+ irradiation

  • Ding, Xiao-Yu (Institute of Laser Advanced Manufacturing, Zhejiang University of Technology) ;
  • Xu, Qiu (Institute for Integrated Radiation and Nuclear Science, Kyoto University) ;
  • Zhu, Xiao-yong (School of Materials Science and Engineering, Hefei University of Technology) ;
  • Luo, Lai-Ma (School of Materials Science and Engineering, Hefei University of Technology) ;
  • Huang, Jian-Jun (Key Laboratory of Optoelectronic Devices and Systems of Ministry of Education and Guangdong Province, College of Optoelectronic Engineering, Shenzhen University) ;
  • Yu, Bin (Key Laboratory of Optoelectronic Devices and Systems of Ministry of Education and Guangdong Province, College of Optoelectronic Engineering, Shenzhen University) ;
  • Gao, Xiang (Institute of Plasma Physics, Chinese Academy of Sciences) ;
  • Li, Jian-Gang (Institute of Plasma Physics, Chinese Academy of Sciences) ;
  • Wu, Yu-Cheng (School of Materials Science and Engineering, Hefei University of Technology)
  • Received : 2019.09.23
  • Accepted : 2020.05.23
  • Published : 2020.12.25
Download PDF
⟨ Previous Next ⟩

Abstract

Oxide dispersion-strengthened materials W-1wt%Pr2O3 and W-1wt%La2O3 were synthesized by wet chemical method and spark plasma sintering. The field emission scanning electron microscopy (FE-SEM) analysis, XRD and Vickers microhardness measurements were conducted to characterize the samples. The irradiations were carried out with a 5 keV helium ion beam to fluences up to 5.0 × 1021 ions/m2 under 600 ℃ using the low-energy ion irradiation system. Transmission electron microscopy (TEM) study was performed to investigate the microstructural evolution in W-1wt%Pr2O3 and W-1wt%La2O3. At 1.0 × 1020 He+/m2, the average loops size of the W-1wt%Pr2O3 was 4.3 nm, much lower than W-1wt% La2O3 of 8.5 nm. However, helium bubbles were not observed throughout in both doped W materials. The effects of pre-irradiation with 1.0 × 1021 He+/m2 on trapping of injected deuterium in doped W was studied by thermal desorption spectrometry (TDS) technique using quadrupole mass spectrometer. Compared with the samples without He+ pre-irradiation, deuterium (D) retention of doped W materials increased after He+ irradiation, whose retention was unsaturated at the damage level of 1.0 × 1022D2+/m2. The present results implied that irradiation effect of He+ ions must be taken into account to evaluate the deuterium retention in fusion material applications.

Keywords

Acknowledgement

This work is supported by National Magnetic Confinement Fusion Program (Grant No. 2014GB121001), National Natural Science Foundation of China (Grant No. 51574101 and 51474083), the Fundamental Research Funds for the Central Universities (PA2018GDQT0010), and the 111 Project (B18018). This study is supported by the Open Foundation of Key Laboratory of Advanced Functional Materials and Devices of the Anhui Province, and Double First Class enhancing independent innovation and social service capabilities of Hefei University of Technology (Grant No. 4500-411104/011). This work was partly supported by JSPS KAKENHI Grant Number JP20K03900.

References

  1. A. Xu, D.E.J. Armstrong, C. Beck, M.P. Moody, G.D.W. Smith, P.A.J. Bagot, S.G. Roberts, Ion-irradiation induced clustering in W-Re-Ta, W-Re and W-Ta alloys: an atom probe tomography and nanoindentation study, Acta Mater. 124 (2017) 71-78.
  2. X.X. Hu, T. Koyanagi, M. Fukuda, Y. Katoh, L.L. Snead, B.D. Wirth, Defect evolution in single crystalline tungsten following low temperature and low dose neutron irradiation, J. Nucl. Mater. 470 (2016) 278-289.
  3. S.J. Zinkle, L.L. Snead, Designing radiation resistance in materials for fusion energy, Annu. Rev. Mater. Res. 44 (1) (2014) 241-267.
  4. T. Toyama, K. Ami, K. Inoue, Y. Nagai, K. Sato, Q. Xu, Y. Hatano, Deuterium trapping at vacancy clusters in electron/neutron-irradiated tungsten studied by positron annihilation spectroscopy, J. Nucl. Mater. 499 (2018) 464-470.
  5. O. El-Atwani, E. Esquivel, M. Efe, E. Aydogan, Y.Q. Wang, E. Martinez, S.A. Maloy, Loop and void damage during heavy ion irradiation on nanocrystalline and coarse grained tungsten: microstructure, effect of dpa rate, temperature, and grain size, Acta Mater. 149 (2018) 206-219.
  6. S. Das, D.E.J. Armstrong, Y. Zayachuk, W. Liu, R. Xu, F. Hofmann, The effect of helium implantation on the deformation behaviour of tungsten: X-ray microdiffraction and nanoindentation, Scripta Mater. 146 (2018) 335-339.
  7. W.J. Qin, F. Ren, R.P. Doerner, G. Wei, Y.W. Lv, S. Chang, M. Tang, H.Q. Deng, C.Z. Jiang, Y.Q. Wang, Nanochannel structures in W enhance radiation tolerance, Acta Mater. 153 (2018) 147-155.
  8. E. Gao, W. Nadvornick, R. Doerner, N.M. Ghoniem, The influence of lowenergy helium plasma on bubble formation in micro-engineered tungsten, J. Nucl. Mater. 501 (2018) 319-328.
  9. S. Kajita, W. Sakaguchi, N. Ohno, N. Yoshida, T. Saeki, Formation process of tungsten nanostructure by the exposure to helium plasma under fusion relevant plasma conditions, Nucl. Fusion 49 (9) (2009), 095005.
  10. M.J. Baldwin, R.P. Doerner, Formation of helium induced nanostructure 'fuzz' on various tungsten grades, J. Nucl. Mater. 404 (2010) 165-173.
  11. L. Huang, L. Jiang, T.D. Topping, C. Dai, X. Wang, R. Carpenter, C. Haines, J.M. Schoenung, In situ oxide dispersion strengthened tungsten alloys with high compressive strength and high strain-to-failure, Acta Mater. 122 (2017) 19-31.
  12. M. Fukuda, A. Hasegawa, S. Nogami, K. Yabuuchi, Microstructure development of dispersion-strengthened tungsten due to neutron irradiation, J. Nucl. Mater. 449 (2014) 213-218.
  13. O. El-Atwani, J.A. Hinks, G. Greaves, S. Gonderman, T. Qiu, M. Efe, J.P. Allain, Insitu TEM observation of the response of ultrafine- and nanocrystalline-grained tungsten to extreme irradiation environments, Sci. Rep. 4 (2014) 4716.
  14. M. Samaras, P.M. Derlet, H. Van Swygenhoven, M. Victoria, Radiation damage near grain boundaries, Philos. Mag. A 83 (2003) 3599-3607.
  15. H. Kurishita, S. Matsuo, H. Arakawa, S. Kobayashi, K. Nakai, T. Takida, K. Takebe, M. Kawai, Superplastic deformation in W-0.5wt.%TiC with approximately 0.1 mm grain size, Mater. Sci. Eng. 477 (2008) 162-167.
  16. S. Wahlberg, M.A. Yar, M.O. Abuelnaga, H.G. Salem, M. Johnsson, M. Muhammed, Fabrication of nanostructured W-Y2O3 materials by chemical methods, J. Mater. Chem. 22 (2012) 12622-12628.
  17. R.G. Chaudhuri, S. Paria, Core/shell nanoparticles: classes, properties, synthesis mechanisms, characterization, and applications, Chem. Rev. 112 (2012) 2373-2433.
  18. M.A. Yar, S. Wahlberg, H. Bergqvist, H.G. Salem, M. Johnsson, M. Muhammed, Chemically produced nanostructured ODSelanthanum oxideetungsten composites sintered by spark plasma, J. Nucl. Mater. 408 (2011) 129-135.
  19. R.E. Stoller, M.B. Toloczko, G.S. Was, A.G. Certain, S. Dwaraknath, F.A. Garner, On the use of SRIM for computing radiation damage exposure, Nucl. Instrum. Methods Phys. Res. B 310 (2013) 75-80.
  20. N. Yoshida, H. Iwakiri, K. Tokunaga, T. Baba, Impact of low energy helium irradiation on plasma facing metals, J. Nucl. Mater. 337-339 (2005) 946-950.
  21. O. El-Atwani, E. Esquivel, M. Efe, E. Aydogan, Y.Q. Wang, E. Martinez, S.A. Maloy, Loop and void damage during heavy ion irradiation on nanocrystalline and coarse grained tungsten: microstructure, effect of dpa rate, temperature, and grain size, Acta Mater. 149 (2018) 206-219.
  22. H. Iwakiri, K. Yasunaga, K. Morishita, N. Yoshida, Microstructure evolution in tungsten during low-energy helium ion irradiation, J. Nucl. Mater. 283-287 (2000) 1134-1138.
  23. T. Tanabe, Review of hydrogen retention in tungsten, Phys. Scripta T159 (2014), 014044.
  24. H.T. Lee, A.A. Haasz, J.W. Davis, R.G. Macaulay-Newcombe, D.G. Whyte, G.M. Wright, Hydrogen and helium trapping in tungsten under simultaneous irradiations, J. Nucl. Mater. 363-365 (2007) 898-903.
  25. H. Iwakiri, K. Morishita, N. Yoshida, Effects of helium bombardment on the deuterium behavior in tungsten, J. Nucl. Mater. 307-311 (2002) 135-138.
  26. I.I. Arkhipov, S.L. Kanashenko, V.M. Sharapov, R.Kh Zalavutdinov, A.E. Gorodetsky, Deuterium trapping in ion-damaged tungsten single crystal, J. Nucl. Mater. 363-365 (2007) 1168-1172.

Cited by

  1. Enhanced mechanical properties and interface structure characterization of W-La2O3 alloy designed by an innovative combustion-based approach vol.53, pp.5, 2020, https://doi.org/10.1016/j.net.2020.11.002