Conclusion

Graphites and C/C Composites for Generation IV Nuclear Reactors

Figure 1 - Schematic diagram of control bar segments (after [7])

Figure 2 - Schematic diagram of a hot duct (from an internal CEA report)

Figure 3 - Typical nuclear graphite manufacturing process

Figure 4 - Typical structural organization of polycrystalline graphite

Figure 5 - Orientation of coke grains according to the shaping process

Figure 6 - Toyo Tanso process for manufacturing the 2D C/C composite &#34;CX 270-G&#34; from research project JAERI-Research 2002-026

Figure 7 - Impact of defects on a and c mesh parameters of graphite single crystals

Figure 8 - Impact of defects on crystallite dimensions in graphite coke grains

Figure 9 - Dimensional variations of spun quasi-isotropic graphite (P3JHAN) as a function of fluence, for different irradiation temperatures (after [24])

Figure 10 - Evolution of thermal conductivity as a function of fluence at different measurement temperatures for IG-110 isotropic graphite irradiated at 600°C (based on data from [27]).

Figure 11 - Thermal conductivity of spun quasi-isotropic graphite (P3JHAN) as a function of fluence at different irradiation temperatures (based on data from [28])

Figure 12 - Evolution of Young&#039;s modulus of spun quasi-isotropic graphite (P3JHAN) as a function of fluence for different irradiation temperatures (based on data from [35])

Figure 13 - Evolution of macroscopic volume and Young&#039;s modulus of quasi-isotropic graphite (ATR-2E) as a function of fluence (based on data from [36])

Figure 14 - Dimensional variations of C/C composites as a function of temperature and irradiation dose