The irradiation response of ZrC ceramics under 10 MeV Au3+ ion irradiation at 800 ºC

作者: Raul Florez , Miguel L. Crespillo , Xiaoqing He , Tommi A. White , Gregory Hilmas

DOI: 10.1016/J.JEURCERAMSOC.2020.01.025

关键词: Analytical chemistryTransmission electron microscopyMaterials scienceMicrostructureOxygenRaman spectroscopyLattice constantIonIrradiationDislocation

摘要: Abstract The microstructural evolution was characterized for ZrC ceramics irradiated with 10 MeV Au3+ ions at 800 °C. Post-irradiation examination showed that did not amorphize doses up to 30 displacement per atoms (dpa). Concurrent oxidation of found occur during ion irradiation. Coarsening the defective microstructure, as a function dose, revealed by transmission electron microscopy analysis. Black dot defects were observed low (0.5 dpa), and tangled dislocation networks formed 5 dpa above. Diffraction analysis change in defect structure occurred close ∼2.5 dpa. lattice parameter dose indicated uptake adventitious oxygen could specimens high doses. Raman spectroscopy an increase non-stochiometry after irradiaton. This work identified specific relationships between microstructure irradiation, revealing mechanisms damage production ZrCx ceramics.

参考文章(58)
Christopher J. Ulmer, Arthur T. Motta, Mark A. Kirk, In situ ion irradiation of zirconium carbide Journal of Nuclear Materials. ,vol. 466, pp. 606- 614 ,(2015) , 10.1016/J.JNUCMAT.2015.08.009
Kazuo Minato, Toru Ogawa, Kazuhiro Sawa, Akiyoshi Ishikawa, Takeshi Tomita, Shozo Iida, Hajime Sekino, Irradiation Experiment on ZrC-Coated Fuel Particles for High-Temperature Gas-Cooled Reactors Nuclear Technology. ,vol. 130, pp. 272- 281 ,(2000) , 10.13182/NT00-A3093
Gokul Vasudevamurthy, Travis W. Knight, Elwyn Roberts, Thad M. Adams, Laboratory production of zirconium carbide compacts for use in inert matrix fuels Journal of Nuclear Materials. ,vol. 374, pp. 241- 247 ,(2008) , 10.1016/J.JNUCMAT.2007.08.016
W A Rachinger, A Correction for the α1 α2 Doublet in the Measurement of Widths of X-ray Diffraction Lines Journal of Scientific Instruments. ,vol. 25, pp. 254- 255 ,(1948) , 10.1088/0950-7671/25/7/125
L. Van Brutzel, J.P. Crocombette, Classical molecular dynamics study of primary damage created by collision cascade in a ZrC matrix Nuclear Instruments & Methods in Physics Research Section B-beam Interactions With Materials and Atoms. ,vol. 255, pp. 141- 145 ,(2007) , 10.1016/J.NIMB.2006.11.048
Yanhui Zhang, Jiemin Wang, Bin Liu, Jingyang Wang, Haibin Zhang, Understanding the Behavior of Native Point Defects in ZrC by First-Principles Calculations Journal of the American Ceramic Society. ,vol. 97, pp. 4024- 4030 ,(2014) , 10.1111/JACE.13196
James F. Ziegler, M.D. Ziegler, J.P. Biersack, SRIM – The stopping and range of ions in matter (2010) Nuclear Instruments & Methods in Physics Research Section B-beam Interactions With Materials and Atoms. ,vol. 268, pp. 1818- 1823 ,(2010) , 10.1016/J.NIMB.2010.02.091
Ming-Jie Zheng, Izabela Szlufarska, Dane Morgan, Defect kinetics and resistance to amorphization in zirconium carbide Journal of Nuclear Materials. ,vol. 457, pp. 343- 351 ,(2015) , 10.1016/J.JNUCMAT.2014.11.059
Dominique Gosset, Mickael Dollé, David Simeone, Gianguido Baldinozzi, Lionel Thomé, Structural behaviour of nearly stoichiometric ZrC under ion irradiation Nuclear Instruments & Methods in Physics Research Section B-beam Interactions With Materials and Atoms. ,vol. 266, pp. 2801- 2805 ,(2008) , 10.1016/J.NIMB.2008.03.121
Yutai Katoh, Gokul Vasudevamurthy, Takashi Nozawa, Lance L. Snead, Properties of Zirconium Carbide for Nuclear Fuel Applications Journal of Nuclear Materials. ,vol. 441, pp. 718- 742 ,(2013) , 10.1016/J.JNUCMAT.2013.05.037