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ORNL–General Atomics partnership on ceramic matrix composites
A memorandum of understanding has been signed by Oak Ridge National Laboratory and General Atomics Electromagnetic Systems (GA-EMS) with the objective of working together on advanced ceramic matrix composite materials for applications in extreme environments. Materials that can withstand extreme temperatures, radiation, corrosion, and mechanical stress are required in aerospace, defense, energy, and other sectors.
According to the agreement, the San Diego–based GA-EMS will use resources from ORNL’s Manufacturing Demonstration Facility to develop “scalable, efficient manufacturing techniques for extreme environment materials including precursors, fibers, composites, and coatings utilized in carbon/carbon (C/C), carbon/silicon carbide (C/SiC), and SiC/SiC composite systems.”
M. Ishii, H. K. Fauske
Nuclear Science and Engineering | Volume 84 | Number 2 | June 1983 | Pages 131-146
Technical Paper | doi.org/10.13182/NSE83-A17719
Articles are hosted by Taylor and Francis Online.
For certain postulated severe accident conditions such as a loss of piping integrity and a loss of heat sink in connection with liquid-metal fast breeder reactor safety analysis, the process of decay heat removal can lead to coolant boiling. For such low-heat-flux/low-flow conditions, a dryout or critical heat flux criterion is required in order to assess the potential for fuel pin failure and melting. Computer codes and full-scale experimental data are not available to completely address this problem at this time. Based on the interpretation of available experimental data and new analyses, it is concluded that a typical subassembly can be safely cooled (avoid dryout) under natural convection conditions for heat fluxes below ∼8 to 10% of the average nominal power; i.e., decay heat power levels can be safely accommodated in the natural convective regime. Furthermore, since this coolability limit is predicted to be rather insensitive to the subcooling value, it follows that the safety case relative to decay heat removal for an intact core geometry also becomes essentially independent of detailed accident conditions such as the potential for temporary stagnated flow or inlet flow reversal conditions.