Composite materials for fusion applications
Ceramic matrix composites, CMCs, are being considered for advanced first-wall and blanket structural applications because of their high-temperature properties, low neutron activation, low density and low coefficient of expansion coupled with good thermal conductivity and corrosion behavior. This paper presents a review and analysis of the hermetic, thermal conductivity, corrosion, crack growth and radiation damage properties of CMCs. It was concluded that the leak rates of a gaseous coolant into the plasma chamber or tritium out of the blanket could exceed design criteria if matrix microcracking causes existing porosity to become interconnected. Thermal conductivities of unirradiated SiC/SiC and C/SiC materials are about 1/2 to 2/3 that of Type 316 SS whereas the thermal conductivity for C/C composites is seven times larger. The thermal stress figure-of-merit value for CMCs exceeds that of Type 316 SS for a single thermal cycle. SiC/SiC composites are very resistant to corrosion and are expected to be compatible with He or Li coolants if the O{sub 2} concentrations are maintained at the appropriate levels. CMCs exhibit subcritical crack growth at elevated temperatures and the crack velocity is a function of the corrosion conditions. The radiation stability of CMCs will depend on the stability of the fiber, microcracking of the matrix, and the effects of gaseous transmutation products on properties. 23 refs., 14 figs., 1 tab.
- Research Organization:
- Pacific Northwest Lab., Richland, WA (United States)
- Sponsoring Organization:
- USDOE; USDOE, Washington, DC (United States)
- DOE Contract Number:
- AC06-76RL01830
- OSTI ID:
- 6129347
- Report Number(s):
- PNL-SA-19391; CONF-911111-7; ON: DE92003001; TRN: 91-033346
- Resource Relation:
- Conference: International conference on fusion reactor materials, Clearwater, FL (United States), 17-22 Nov 1991
- Country of Publication:
- United States
- Language:
- English
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36 MATERIALS SCIENCE
CERAMICS
CORROSION
CRACK PROPAGATION
PHYSICAL RADIATION EFFECTS
THERMAL CONDUCTIVITY
THERMONUCLEAR REACTOR MATERIALS
BREEDING BLANKETS
DAMAGING NEUTRON FLUENCE
FEASIBILITY STUDIES
FIRST WALL
SILICON CARBIDES
CARBIDES
CARBON COMPOUNDS
CHEMICAL REACTIONS
MATERIALS
NEUTRON FLUENCE
PHYSICAL PROPERTIES
RADIATION EFFECTS
REACTOR COMPONENTS
SILICON COMPOUNDS
THERMODYNAMIC PROPERTIES
THERMONUCLEAR REACTOR WALLS
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