skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: Design and strategy for next-generation silicon carbide composites for nuclear energy

Journal Article · · Journal of Nuclear Materials
ORCiD logo [1]; ORCiD logo [1];  [2]
  1. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Materials Science & Technology Division
  2. National Inst. for Quantum and Radiological Science and Technology, Aomori (Japan)

Silicon carbide (SiC) ceramic-based composites continue to be attractive material options for fusion in-vessel components and fission reactor core structures because of their exceptional high-temperature capability and favorable neutronic properties. As performance data accumulates, the limitations of the current generation of nuclear-grade SiC composites are becoming more apparent. These limitations mainly involve strength degradation during high-dose neutron irradiation. In this paper, we discuss several options for improving the performance of the next generation of SiC composites to enhance the radiation resistance, along with new experimental results on neutron irradiation resistance. The main emphasis is on the selection of the fibers and the design and development of alternative interphase layers for advanced composites.

Research Organization:
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
Sponsoring Organization:
USDOE Office of Science (SC), Fusion Energy Sciences (FES); USDOE Office of Nuclear Energy (NE), Nuclear Fuel Cycle and Supply Chain. Advanced Fuel Campaign; National Institutes for Quantum and Radiological Science and Technology (QST)
Grant/Contract Number:
AC05-00OR22725; NFE-10-02779
OSTI ID:
1649292
Alternate ID(s):
OSTI ID: 1639133
Journal Information:
Journal of Nuclear Materials, Vol. 540; ISSN 0022-3115
Publisher:
ElsevierCopyright Statement
Country of Publication:
United States
Language:
English

References (46)

X-ray diffractometry and high-resolution electron microscopy of neutron-irradiated SiC to a fluence of 1.9×1027 n/m2 journal March 1998
Interface structures in beta‐silicon carbide thin films journal January 1987
Analysis of crack deviation in ceramic matrix composites and multilayers based on the Cook and Gordon mechanism journal August 2007
Swelling and time-dependent crack growth in SiC/SiC composites journal August 2007
Materials challenges in nuclear energy journal February 2013
Handbook of SiC properties for fuel performance modeling journal September 2007
Influence of residual stresses on fracture and delamination of thin hard coatings journal October 1999
Characterization of SiC–SiC composites for accident tolerant fuel cladding journal November 2015
Mechanical properties of SiC composites neutron irradiated under light water reactor relevant temperature and dose conditions journal October 2017
Thermal and Environmental Barrier Coatings for SiC/SiC CMCs in Aircraft Engine Applications* journal October 2004
Influence of an original manufacturing process on the properties and microstructure of SiC/SiC tubular composites journal August 2019
High-dose neutron irradiation of Hi-Nicalon Type S silicon carbide composites. Part 2: Mechanical and physical properties journal July 2015
High-dose, intermediate-temperature neutron irradiation effects on silicon carbide composites with varied fiber/matrix interfaces journal July 2019
Stress Field in a Coated Continuous Fiber Composite Subjected to Thermo-Mechanical Loadings journal November 1985
Influence of Interface Characteristics on the Mechanical Properties of Hi-Nicalon type-S or Tyranno-SA3 Fiber-Reinforced SiC/SiC Minicomposites: Influence of Interface Characteristics on the Mechanical Properties journal February 2010
Interface Design for Oxidation-Resistant Ceramic Composites journal November 2002
SYLRAMIC™ SiC fibers for CMC reinforcement journal December 2000
Rayleigh and Raman images of the bulk/surface nanostructure of SiC based fibres journal March 2004
Thermodynamic Calculations for the Chemical Vapor Deposition of Silicon Carbide journal August 1983
C-ring testing of nuclear grade silicon carbide composites at temperatures up to 1900 °C journal August 2019
A constitutive model for anisotropic damage in fiber-composites journal April 1995
Nanoscale multilayered and porous carbide interphases prepared by pressure-pulsed reactive chemical vapor deposition for ceramic matrix composites journal June 2013
Recent progress in the development of SiC composites for nuclear fusion applications journal December 2018
Tensile and Stress-Rupture Behavior of SiC/SiC Minicomposite Containing Chemically Vapor Deposited Zirconia Interphase journal September 2004
Multiple zirconia interphase for SiC/SiCf composites journal January 2011
The effect of neutron irradiation on the fiber/matrix interphase of silicon carbide composites journal February 2009
Irradiation-induced shrinkage of highly crystalline SiC fibers journal January 2015
The critical issues of SiC materials for future nuclear systems journal January 2018
Modeling Environmental Degradation of SiC-Based Fibers journal February 2016
Swift heavy ion-induced swelling and damage in yttria-stabilized zirconia journal April 2007
The physics and mechanics of fibre-reinforced brittle matrix composites journal August 1994
Re-defining failure envelopes for silicon carbide composites based on damage process analysis by acoustic emission journal October 2013
Mechanical, Thermal, and Microstructural Properties of Neutron-Irradiated SiC journal July 1983
Evaluation of neutron irradiated silicon carbide and silicon carbide composites journal September 2007
Continuous SiC fiber, CVI SiC matrix composites for nuclear applications: Properties and irradiation effects journal May 2014
Fatigue of three advanced SiC/SiC ceramic matrix composites at 1200°C in air and in steam journal August 2017
Thermal conductivity of SiC microwires: Effect of temperature and structural domain size uncovered by 0 K limit phonon scattering journal July 2018
Thermodynamic Analysis and Kinetic Implications of Chemical Vapor Deposition of Sic from Si-C-C1-H Gas Systems journal April 1985
Thermodynamics, Kinetics, and Microstructure of Laser Chemical Vapor Deposition of SiC journal February 2006
Formation of Ti 3 SiC 2 interphase coating on SiC f /SiC composite by electrophoretic deposition journal September 2017
Mechanical property degradation of high crystalline SiC fiber–reinforced SiC matrix composite neutron irradiated to ∼100 displacements per atom journal April 2018
High temperature properties of SiC and diamond CVD-monofilaments journal July 2005
Low dose irradiation performance of SiC interphase SiC/SiC composites journal March 1998
Measurement of the effect of radiation damage to ceramic composite interfacial strength journal September 1992
Finite element analysis of damaged woven fabric composite materials journal February 2003
Neutron-irradiation creep of silicon carbide materials beyond the initial transient journal September 2016