Skip to main content
U.S. Department of Energy
Office of Scientific and Technical Information

Multiscale characterization of irradiation behaviour of ion-irradiated SiC/SiC composites

Journal Article · · Acta Materialia
 [1];  [1];  [1];  [1];  [2];  [3]
  1. Univ. of Tennessee, Knoxville, TN (United States). Department of Materials Science and Engineering
  2. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Materials Science and Technology Division
  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
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.
Research Organization:
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
Sponsoring Organization:
USDOE; USDOE Office of Nuclear Energy (NE)
Grant/Contract Number:
AC05-00OR22725; NE0008577
OSTI ID:
1474616
Alternate ID(s):
OSTI ID: 1636946
OSTI ID: 22744880
Journal Information:
Acta Materialia, Journal Name: Acta Materialia Journal Issue: C Vol. 161; ISSN 1359-6454
Publisher:
ElsevierCopyright Statement
Country of Publication:
United States
Language:
English

References (25)

Spatial variation in void volume during charged particle bombardment — the effects of injected interstitials journal December 1979
Critical radius for bias-driven swelling — a further analysis and its application to bimodal cavity size distributions journal August 1983
Suppression of void nucleation by injected interstitials during heavy ion bombardment journal April 1984
Characterisation of radiation-damage microstructures by TEM journal October 1994
Neutron irradiation effects on the density, tensile properties and microstructural changes in Hi-Nicalon™ and Sylramic™ SiC fibers journal March 1998
Dimensional stability and tensile strength of irradiated Nicalon-CG and Hi-Nicalon fibers journal March 1998
Radiation response of SiC-based fibers journal October 1998
Amorphization of SiC under ion and neutron irradiation journal May 1998
Irradiation-induced shrinkage of highly crystalline SiC fibers journal January 2015
High temperature ion irradiation effects in MAX phase ceramics journal February 2016
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
Current status and critical issues for development of SiC composites for fusion applications journal August 2007
Swelling of SiC at intermediate and high irradiation temperatures journal August 2007
Handbook of SiC properties for fuel performance modeling journal September 2007
Thermophysical and mechanical properties of near-stoichiometric fiber CVI SiC/SiC composites after neutron irradiation at elevated temperatures journal August 2010
Au ion irradiation of various silicon carbide fiber-reinforced SiC matrix composites journal August 2013
Silicon carbide composite for light water reactor fuel assembly applications journal May 2014
Accident tolerant fuels for LWRs: A perspective journal May 2014
High dose neutron irradiation of Hi-Nicalon Type S silicon carbide composites, Part 1: Microstructural evaluations journal July 2015
Cluster dynamics modeling and experimental investigation of the effect of injected interstitials journal December 2017
Accident tolerant fuel cladding development: Promise, status, and challenges journal April 2018
New ion beam materials laboratory for materials modification and irradiation effects research journal November 2014
EFTEM spectrum imaging at high-energy resolution journal October 2006
EFTEM assistant: A tool to understand the limitations of EFTEM journal April 2007
Feret‘s Statistical Diameter as a Measure of Particle Size journal August 1948

Cited By (1)

Microstructure of SiC fibers by swift heavy ion beam irradiation journal July 2019