Composite materials for fusion applications
Description
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 O2 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
Availability note (English)
MF available from INIS under the Report Number; OSTI as DE92003001; NTIS; INIS; US Govt. Printing Office Dep.Files
23024414.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 48 p.
- Report number
- PNL-SA--19391
Conference
- Title
- International conference on fusion reactor materials.
- Dates
- 17-22 Nov 1991.
- Place
- Clearwater, FL (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 23024414
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY; S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BREEDING BLANKETS; CERAMICS; CORROSION; CRACK PROPAGATION; DAMAGING NEUTRON FLUENCE; FEASIBILITY STUDIES; FIRST WALL; PHYSICAL RADIATION EFFECTS; SILICON CARBIDES; THERMAL CONDUCTIVITY; THERMONUCLEAR REACTOR MATERIAL
- Descriptors DEC
- CARBIDES; CARBON COMPOUNDS; CHEMICAL REACTIONS; MATERIALS; NEUTRON FLUENCE; PHYSICAL PROPERTIES; RADIATION EFFECTS; SILICON COMPOUNDS; THERMODYNAMIC PROPERTIES; THERMONUCLEAR REACTOR WALLS
Optional Information
- Contract/Grant/Project number
- Contract AC06-76RL01830
- Funding organization
- USDOE, Washington, DC (United States).
- Secondary number(s)
- CONF-911111--7.