Void evolution in tungsten and tungsten-5wt.% tantalum under in-situ proton irradiation at 800 and 1000 °C

作者: Iuliia Ipatova , RW Harrison , SE Donnelly , MJD Rushton , SC Middleburgh

DOI: 10.1016/J.JNUCMAT.2019.07.030

关键词:

摘要: Abstract We have probed void evolution in polycrystalline W and W-5wt.%Ta material at 800 1000 °C, by transmission electron microscopy during in-situ irradiation with a 40 keV proton beam. The presence of radiation-induced dislocation loops was not observed prior to formation those elevated temperatures. damaged microstructure characterised the population randomly distributed voids, whose number density reduces when temperature increases. Soft impingement voids becomes noticeable damage levels ≥0.2 dpa. In contrast, excess free vacancies irradiated 800 °C only leads visible this TEM study (≥2 nm) after post-irradiation annealing sample 1000 °C. Solute Ta atoms also cause significant increase comparing both materials gradual progression towards saturation average size Moreover, we detected progressive transition from spherical faceted shape present ≥0.3

参考文章(65)
Antonella Li-Puma, Marianne Richou, Philippe Magaud, Marc Missirlian, Eliseo Visca, Vincenzo Pericoli Ridolfini, Potential and limits of water cooled divertor concepts based on monoblock design as possible candidates for a DEMO reactor Fusion Engineering and Design. ,vol. 88, pp. 1836- 1843 ,(2013) , 10.1016/J.FUSENGDES.2013.05.114
X. Yi, M.L. Jenkins, M. Briceno, S.G. Roberts, Z. Zhou, M.A. Kirk, In situ study of self-ion irradiation damage in W and W-5Re at 500 °C Philosophical Magazine. ,vol. 93, pp. 1715- 1738 ,(2013) , 10.1080/14786435.2012.754110
D E J Armstrong, A J Wilkinson, S G Roberts, Mechanical properties of ion-implanted tungsten–5 wt% tantalum Physica Scripta. ,vol. 2011, pp. 014076- ,(2011) , 10.1088/0031-8949/2011/T145/014076
B. N. Singh, On the influence of grain boundaries on void growth Philosophical Magazine. ,vol. 28, pp. 1409- 1413 ,(1973) , 10.1080/14786437308228009
L.K. Keys, J. Moteff, Neutron irradiation and defect recovery of tungsten Journal of Nuclear Materials. ,vol. 34, pp. 260- 280 ,(1970) , 10.1016/0022-3115(70)90193-5
Francesco Ferroni, Xiaoou Yi, Kazuto Arakawa, Steven P. Fitzgerald, Philip D. Edmondson, Steve G. Roberts, High temperature annealing of ion irradiated tungsten Acta Materialia. ,vol. 90, pp. 380- 393 ,(2015) , 10.1016/J.ACTAMAT.2015.01.067
Michael Rieth, Sergei L Dudarev, SM Gonzalez De Vicente, J Aktaa, T Ahlgren, S Antusch, DEJ Armstrong, M Balden, Nadine Baluc, M-F Barthe, WW Basuki, M Battabyal, CS Becquart, D Blagoeva, H Boldyryeva, J Brinkmann, M Celino, L Ciupinski, JB Correia, A De Backer, Christophe Domain, E Gaganidze, C García-Rosales, J Gibson, Mark R Gilbert, S Giusepponi, B Gludovatz, H Greuner, K Heinola, T Höschen, A Hoffmann, N Holstein, F Koch, W Krauss, Hongfei Li, S Lindig, J Linke, Ch Linsmeier, P López-Ruiz, H Maier, J Matejicek, TP Mishra, Mamoun Muhammed, A Muñoz, Marek Muzyk, Kai Nordlund, D Nguyen-Manh, J Opschoor, N Ordás, T Palacios, G Pintsuk, R Pippan, J Reiser, J Riesch, SG Roberts, L Romaner, Marcin Rosiński, M Sanchez, W Schulmeyer, H Traxler, A Ureña, JG Van Der Laan, L Veleva, Sverker Wahlberg, M Walter, T Weber, T Weitkamp, S Wurster, Mazher Ahmed Yar, JH You, A Zivelonghi, None, Recent progress in research on tungsten materials for nuclear fusion applications in Europe Journal of Nuclear Materials. ,vol. 432, pp. 482- 500 ,(2013) , 10.1016/J.JNUCMAT.2012.08.018
Xiaoou Yi, Michael L. Jenkins, Khalid Hattar, Philip D. Edmondson, Steve G. Roberts, Characterisation of radiation damage in W and W-based alloys from 2 MeV self-ion near-bulk implantations Acta Materialia. ,vol. 92, pp. 163- 177 ,(2015) , 10.1016/J.ACTAMAT.2015.04.015
P. E. A. Turchi, A. Gonis, V. Drchal, J. Kudrnovský, First-principles study of stability and local order in substitutional Ta-W alloys Physical Review B. ,vol. 64, ,(2001) , 10.1103/PHYSREVB.64.085112