Multiscale characterization of irradiation behaviour of ion-irradiated SiC/SiC composites
Abstract
Here, the irradiation tolerance of SiC/SiC composites was studied using 10 MeV Au ion irradiations at 350 °C, for surface doses between 1 and 50 displacements per atom (dpa). Atomic force microscopy and optical profilometry revealed irradiation-induced axial and radial shrinkage of SiC-fibers. At 50 dpa, net fiber shrinkage reached 2.8 ± 0.3%. We conclude that the primary cause of SiC-fiber shrinkage in SiC/SiC composites is the irradiation-induced loss of pre-existing carbon packets, which had occupied 2–3% fiber volume in unirradiated state. A compelling evidence of the carbon packet loss was revealed using a combination of state-of-art conventional transmission electron microscopy (TEM), high resolution TEM, energy-filtered TEM and electron energy loss spectroscopy. Additionally, the carbon packet volume fraction decreased with increasing dose, reaching near-complete loss after 50 dpa. Carbon packet loss was further confirmed using Raman spectroscopy where the carbon D and G peaks disappeared after irradiation. In contrast, irradiation-induced swelling of 1 ± 0.5% was observed in the matrix after 50 dpa. The study also shows that up to 50 dpa, the multilayer pyrolytic-carbon (PyC) interface in the composite is highly irradiation tolerant as it maintained its morphology, graphitic nature and showed no signs of amorphization. Additionally, Raman spectroscopymore »
- Authors:
-
[2];
[3]
- Univ. of Tennessee, Knoxville, TN (United States). Department of Materials Science and Engineering
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Materials Science and Technology Division
- Univ. of Tennessee, Knoxville, TN (United States). Department of Materials Science and Engineering; Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Materials Science and Technology Division
- Publication Date:
- Research Org.:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Sponsoring Org.:
- USDOE Office of Nuclear Energy (NE)
- OSTI Identifier:
- 1474616
- Alternate Identifier(s):
- OSTI ID: 1636946
- Grant/Contract Number:
- AC05-00OR22725; NE0008577
- Resource Type:
- Accepted Manuscript
- Journal Name:
- Acta Materialia
- Additional Journal Information:
- Journal Volume: 161; Journal Issue: C; Journal ID: ISSN 1359-6454
- Publisher:
- Elsevier
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 36 MATERIALS SCIENCE; Silicon carbide (SiC); Implantation/irradiation; Transmission electron microscopy (TEM); Carbon; Raman spectroscopy
Citation Formats
Agarwal, Shradha, Duscher, Gerd J M, Zhao, Yajie, Crespillo, Miguel L., Katoh, Yutai, and Weber, William J. Multiscale characterization of irradiation behaviour of ion-irradiated SiC/SiC composites. United States: N. p., 2018.
Web. doi:10.1016/j.actamat.2018.09.012.
Agarwal, Shradha, Duscher, Gerd J M, Zhao, Yajie, Crespillo, Miguel L., Katoh, Yutai, & Weber, William J. Multiscale characterization of irradiation behaviour of ion-irradiated SiC/SiC composites. United States. https://doi.org/10.1016/j.actamat.2018.09.012
Agarwal, Shradha, Duscher, Gerd J M, Zhao, Yajie, Crespillo, Miguel L., Katoh, Yutai, and Weber, William J. Tue .
"Multiscale characterization of irradiation behaviour of ion-irradiated SiC/SiC composites". United States. https://doi.org/10.1016/j.actamat.2018.09.012. https://www.osti.gov/servlets/purl/1474616.
@article{osti_1474616,
title = {Multiscale characterization of irradiation behaviour of ion-irradiated SiC/SiC composites},
author = {Agarwal, Shradha and Duscher, Gerd J M and Zhao, Yajie and Crespillo, Miguel L. and Katoh, Yutai and Weber, William J.},
abstractNote = {Here, the irradiation tolerance of SiC/SiC composites was studied using 10 MeV Au ion irradiations at 350 °C, for surface doses between 1 and 50 displacements per atom (dpa). Atomic force microscopy and optical profilometry revealed irradiation-induced axial and radial shrinkage of SiC-fibers. At 50 dpa, net fiber shrinkage reached 2.8 ± 0.3%. We conclude that the primary cause of SiC-fiber shrinkage in SiC/SiC composites is the irradiation-induced loss of pre-existing carbon packets, which had occupied 2–3% fiber volume in unirradiated state. A compelling evidence of the carbon packet loss was revealed using a combination of state-of-art conventional transmission electron microscopy (TEM), high resolution TEM, energy-filtered TEM and electron energy loss spectroscopy. Additionally, the carbon packet volume fraction decreased with increasing dose, reaching near-complete loss after 50 dpa. Carbon packet loss was further confirmed using Raman spectroscopy where the carbon D and G peaks disappeared after irradiation. In contrast, irradiation-induced swelling of 1 ± 0.5% was observed in the matrix after 50 dpa. The study also shows that up to 50 dpa, the multilayer pyrolytic-carbon (PyC) interface in the composite is highly irradiation tolerant as it maintained its morphology, graphitic nature and showed no signs of amorphization. Additionally, Raman spectroscopy revealed a saturation of TEM invisible disorder at 1 dpa for both ultra-fine grains of the fiber and the larger SiC-matrix grains. However, TEM visible extended defect formation such as dislocation loops were only detected in the larger matrix grains, thereby revealing a potential role of grain size on defect accumulation in SiC.},
doi = {10.1016/j.actamat.2018.09.012},
journal = {Acta Materialia},
number = C,
volume = 161,
place = {United States},
year = {Tue Sep 11 00:00:00 EDT 2018},
month = {Tue Sep 11 00:00:00 EDT 2018}
}
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Works referenced in this record:
Accident tolerant fuels for LWRs: A perspective
journal, May 2014
- Zinkle, S. J.; Terrani, K. A.; Gehin, J. C.
- Journal of Nuclear Materials, Vol. 448, Issue 1-3
Accident tolerant fuel cladding development: Promise, status, and challenges
journal, April 2018
- Terrani, Kurt A.
- Journal of Nuclear Materials, Vol. 501
Silicon carbide composite for light water reactor fuel assembly applications
journal, May 2014
- Yueh, Ken; Terrani, Kurt A.
- Journal of Nuclear Materials, Vol. 448, Issue 1-3
Thermophysical and mechanical properties of near-stoichiometric fiber CVI SiC/SiC composites after neutron irradiation at elevated temperatures
journal, August 2010
- Katoh, Yutai; Snead, Lance L.; Nozawa, Takashi
- Journal of Nuclear Materials, Vol. 403, Issue 1-3
Current status and critical issues for development of SiC composites for fusion applications
journal, August 2007
- Katoh, Y.; Snead, L. L.; Henager, C. H.
- Journal of Nuclear Materials, Vol. 367-370
Radiation response of SiC-based fibers
journal, October 1998
- Youngblood, G. E.; Jones, R. H.; Kohyama, Akira
- Journal of Nuclear Materials, Vol. 258-263
Dimensional stability and tensile strength of irradiated Nicalon-CG and Hi-Nicalon fibers
journal, March 1998
- Henager, C. H.; Youngblood, G. E.; Senor, D. J.
- Journal of Nuclear Materials, Vol. 253, Issue 1-3
Neutron irradiation effects on the density, tensile properties and microstructural changes in Hi-Nicalon™ and Sylramic™ SiC fibers
journal, March 1998
- Osborne, M. C.; Hubbard, C. R.; Snead, L. L.
- Journal of Nuclear Materials, Vol. 253, Issue 1-3
Influence of chemical and physical properties of the last generation of silicon carbide fibres on the mechanical behaviour of SiC/SiC composite
journal, March 2012
- Buet, E.; Sauder, C.; Poissonnet, S.
- Journal of the European Ceramic Society, Vol. 32, Issue 3
High dose neutron irradiation of Hi-Nicalon Type S silicon carbide composites, Part 1: Microstructural evaluations
journal, July 2015
- Perez-Bergquist, Alejandro G.; Nozawa, Takashi; Shih, Chunghao
- Journal of Nuclear Materials, Vol. 462
Irradiation-induced shrinkage of highly crystalline SiC fibers
journal, January 2015
- Kondo, Sosuke; Hinoki, Tatsuya; Nonaka, Makoto
- Acta Materialia, Vol. 83
Au ion irradiation of various silicon carbide fiber-reinforced SiC matrix composites
journal, August 2013
- Chaâbane, Nihed; Flem, Marion Le; Tanguy, Morgane
- Journal of Nuclear Materials, Vol. 439, Issue 1-3
New ion beam materials laboratory for materials modification and irradiation effects research
journal, November 2014
- Zhang, Y.; Crespillo, M. L.; Xue, H.
- Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, Vol. 338
Suppression of void nucleation by injected interstitials during heavy ion bombardment
journal, April 1984
- Plumton, D. L.; Wolfer, W. G.
- Journal of Nuclear Materials, Vol. 120, Issue 2-3
Cluster dynamics modeling and experimental investigation of the effect of injected interstitials
journal, December 2017
- Michaut, B.; Jourdan, T.; Malaplate, J.
- Journal of Nuclear Materials, Vol. 496
Spatial variation in void volume during charged particle bombardment — the effects of injected interstitials
journal, December 1979
- Lee, E. H.; Mansur, L. K.; Yoo, M. H.
- Journal of Nuclear Materials, Vol. 85-86
EFTEM spectrum imaging at high-energy resolution
journal, October 2006
- Schaffer, Bernhard; Kothleitner, Gerald; Grogger, Werner
- Ultramicroscopy, Vol. 106, Issue 11-12
EFTEM assistant: A tool to understand the limitations of EFTEM
journal, April 2007
- Lozano-Perez, S.; Titchmarsh, J. M.
- Ultramicroscopy, Vol. 107, Issue 4-5
Feret‘s Statistical Diameter as a Measure of Particle Size
journal, August 1948
- Walton, W. H.
- Nature, Vol. 162, Issue 4113
Characterisation of radiation-damage microstructures by TEM
journal, October 1994
- Jenkins, M. L.
- Journal of Nuclear Materials, Vol. 216
Swelling of SiC at intermediate and high irradiation temperatures
journal, August 2007
- Snead, L. L.; Katoh, Y.; Connery, S.
- Journal of Nuclear Materials, Vol. 367-370
Critical radius for bias-driven swelling — a further analysis and its application to bimodal cavity size distributions
journal, August 1983
- Hishinuma, A.; Mansur, L. K.
- Journal of Nuclear Materials, Vol. 118, Issue 1
Amorphization of SiC under ion and neutron irradiation
journal, May 1998
- Snead, L. L.; Zinkle, S. J.; Hay, J. C.
- Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, Vol. 141, Issue 1-4
Handbook of SiC properties for fuel performance modeling
journal, September 2007
- Snead, Lance L.; Nozawa, Takashi; Katoh, Yutai
- Journal of Nuclear Materials, Vol. 371, Issue 1-3
High temperature ion irradiation effects in MAX phase ceramics
journal, February 2016
- Clark, D. W.; Zinkle, S. J.; Patel, M. K.
- Acta Materialia, Vol. 105
Works referencing / citing this record:
Microstructure of SiC fibers by swift heavy ion beam irradiation
journal, July 2019
- Song, Yin; Zhang, Chong-Hong; Yang, Yi-Tao
- Modern Physics Letters B, Vol. 33, Issue 20