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Title: Composite materials for fusion applications

Abstract

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,more » microcracking of the matrix, and the effects of gaseous transmutation products on properties. 23 refs., 14 figs., 1 tab.« less

Authors:
; ;
Publication Date:
Research Org.:
Pacific Northwest Lab., Richland, WA (United States)
Sponsoring Org.:
USDOE; USDOE, Washington, DC (United States)
OSTI Identifier:
6129347
Report Number(s):
PNL-SA-19391; CONF-911111-7
ON: DE92003001; TRN: 91-033346
DOE Contract Number:
AC06-76RL01830
Resource Type:
Conference
Resource Relation:
Conference: International conference on fusion reactor materials, Clearwater, FL (United States), 17-22 Nov 1991
Country of Publication:
United States
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; Ma; 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; 700480* - Fusion Technology- Component Development; Materials Studies- (1992-); 700420 - Fusion Technology- Plasma-Facing Components- (1992-); 360204 - Ceramics, Cermets, & Refractories- Physical Properties; 360206 - Ceramics, Cermets, & Refractories- Radiation Effects; 360203 - Ceramics, Cermets, & Refractories- Mechanical Properties; 360205 - Ceramics, Cermets, & Refractories- Corrosion & Erosion

Citation Formats

Jones, R.H., Henager, C.H. Jr., and Hollenberg, G.W. Composite materials for fusion applications. United States: N. p., 1991. Web.
Jones, R.H., Henager, C.H. Jr., & Hollenberg, G.W. Composite materials for fusion applications. United States.
Jones, R.H., Henager, C.H. Jr., and Hollenberg, G.W. 1991. "Composite materials for fusion applications". United States. doi:. https://www.osti.gov/servlets/purl/6129347.
@article{osti_6129347,
title = {Composite materials for fusion applications},
author = {Jones, R.H. and Henager, C.H. Jr. and Hollenberg, G.W.},
abstractNote = {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.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = 1991,
month =
}

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