Skip to main content
Log in

Carbon–Carbon Composite Materials

  • Published:
Inorganic Materials Aims and scope

Abstract

Data are summarized on the performance characteristics and properties of Russian-produced and foreign carbon–carbon composite materials for various engineering applications. The effect of neutron irradiation on their macroscopic properties and structure is examined. The relationships between the radiation-induced dimensional changes and properties of the composites are established, which can be used in assessing the engineering performance and optimizing the fabrication of carbon–carbon composites.

This is a preview of subscription content, log in via an institution to check access.

Access this article

Price excludes VAT (USA)
Tax calculation will be finalised during checkout.

Instant access to the full article PDF.

Similar content being viewed by others

REFERENCES

  1. Normy rascheta na prochnost' tipovykh uzlov i detalei iz grafita uran-grafitovykh kanal'nykh reaktorov (Strength Calculations for Standard Graphite Units of Graphite-Uranium Channel Reactors), Moscow: NIKIET, NIIgrafit, IAE, ChPI, 1991.

  2. Lukina, E.Yu., Teplovoe rasshirenie uglerodnykh materialov (Thermal Expansion of Carbon Materials), Moscow: TsNIIekonominformtsvetmet, 1990.

  3. Virgil'ev, Yu.S. and Kalyagina, I.P., A Technique for Assessing the Dimensional Stability of Structural Graphite under Irradiation, Konstr. Mater. Osn. Ugleroda, 1978, no. 13, pp. 123–128.

  4. Virgil'ev, Yu.S., Experimental Evaluation of the Radiation Resistance of Reactor Graphite, Perspekt. Mater., 2000, no. 4, pp. 41–47.

  5. Khabibulaev, P.K., Basic and Applied Research at the VVR-SM at the Institute of Nuclear Physics, Uzb. SSR Academy of Sciences, At. Energ., 1988, vol. 64, no. 5, p. 338.

    Google Scholar 

  6. Karpukhin, V.I. and Nikolaenko, V.A., Izmerenie temperatury s pomoshch'yu obluchennogo almaza (Temperature Measurements Using Irradiated Diamond), Moscow: Atomizdat, 1971.

    Google Scholar 

  7. Goncharov, V.V., Burdakov, N.S., Virgil'ev, Yu.S., et al., Deistvie oblucheniya na grafit yadernykh reaktorov (Irradiation Behavior of Reactor Graphite), Moscow: Atomizdat, 1978.

    Google Scholar 

  8. Konkin, A.A. and Varshavskaya, V.Ya., Khim. Volokna, 1974, no. 3, p. 17.

  9. Andrianov, K.A., Vlasov, K.P., Kostikov, V.I., et al., Potential Applications of Carbon-Carbon Composite Materials in Nuclear Power Engineering, At. Energ., 1979, vol. 46, no. 6, p. 406.

    Google Scholar 

  10. Ponomareva, E.V. and Virgil'ev, Yu.S., Irradiation Effects on the Structure and Properties of Carbon Fibers, Fiz. Khim. Obrab. Mater., 1995, no. 2, pp. 5–18.

  11. Burchell, T.D., The Effects of Neutron Irradiation on the Structure and Properties of Graphite, Proc. Mater. Specialist Meet. on Materials Data Base, Garching, 1990.

  12. Bowers, D.A. and Sopp, J.W., Carbon-Based Materials: Thermal Development Testing and Selection Process for First Wall and Divertor Applications, Proc. 5th Int. Conf. on Fusion Reactor Materials, ICFRM-5, Clearwater, 1991, pp. 305–308. INORGANIC MATERIALS Vol. 40 Suppl. 1 2004 CARBON-CARBON COMPOSITE MATERIALS S49

    Google Scholar 

  13. Kuznetsov, D.A., Kurolenkin, E.I., Virgil'ev, Yu.S., et al., Effect of Low-Temperature (340-360?C) Neutron Irradiation on the Structure and Properties of Carbon Fibers, Mezhdunarodnaya konferentsiya po radiatsionnomu materialovedeniyu (Int. Conf. on the Irradiation Behavior of Materials), Alushta, 1990 (Kharkov: Khar'kov. Fiziko-Tekh. Inst., 1991, vol. 8, pp. 83-90).

  14. Kurolenkin, E.I., Virgil'ev, Yu.S., and Kuznetsov, D.A., Effect of High-Temperature Neutron Irradiation on the Structure and Properties of Carbon Fibers, Fiz. Khim. Obrab. Mater., 1992, no. 4, pp. 18–21.

  15. Virgil'ev, Yu.S., Effect of Neutron Irradiation on the Properties of Pyrolytic Carbon, Khim. Tverd. Topl. (Moscow), 1993, no. 3, pp. 64–75.

  16. Virgil'ev, Yu.S., Asaturov, S.A., Kurolenkin, E.I., and Makarchenko, V.G., Irradiation Effects on the Structure of Glassy Carbon, Khim. Tverd. Topl. (Moscow), 1992, no. 3, pp. 106–112.

  17. Bullok, Irradiation Induced Dimensional Changes of Poorly Crystalline Carbon, Carbon, 1979, vol. 17, no. 6, pp. 447–452.

    Article  Google Scholar 

  18. Virgil'ev, Yu.S. and Lebedev, I.G., Radiation Resistance of Reactor Graphites Based on Inexpensive Raw Materials, Neorg. Mater., 2002, vol. 38, no. 9, pp. 1060–1064 [Inorg. Mater.(Engl. Transl.), vol. 38, no. 9, pp. 890-894].

    Google Scholar 

  19. Everett, M.R., Graphite and Matrix Materials for Very High Temperature Reactors, Int. Conf., London, 1974, p. 46/1.

  20. Virgil'ev, Yu.S. and Lebedev, I.G., Effect of Neutron Irradiation on Properties of Glassy Carbon, Neorg. Mater., 2002, vol. 38, no. 7, pp. 810–816 [Inorg. Mater.(Engl. Transl.), vol. 38, no. 7, pp. 668-673].

    Google Scholar 

  21. Kostikov, V.I., Carbon-Carbon Composite Materials, Zh. Vses. Khim. O-va. im. D. I. Mendeleeva, 1989, vol. 34, no. 5, pp. 492–501.

    Google Scholar 

  22. Burchell, T.D., A Review of the Properties of Carbon Materials Suitable for MHTGR High-Temperature Control Rods, ORNL/NPP-90/14, 1991.

  23. Lince, J., High Heat Flux Tests on C-Materials, Proc. Japan-US Workshop P-92, Nagoya, 1987, pp. 276–284.

  24. Uglerodnyi kompozit KM-5415 (Carbon Composite KM-5415), Moscow: Vneshtorgizdat, no. 6678MV, 1989.

  25. Dvukhmerno-armirovannyi uglerodnyi kompozit KUMVM-2 (2D-Reinforced Carbon Composite KUM-VM-2), Moscow: Vneshtorgizdat, no. 6677MV, 1989.

  26. Virgil'ev, Yu.S., Ponomareva, E.V., and Ponomarev, O.V., Carbon Materials for Fusion Energy Applications, Perspekt. Mater., 1995, vol. 2, no. 3, pp. 218–227.

    Google Scholar 

  27. Virgil'ev, <del> </del>Yu.S., Vlasov, K.P., and Vlasov, A.K., Radiation Resistance of Carbon-Carbon Composite Materials, At. Energ., 1996, vol. 80, no. 4, pp. 263–266.

    Google Scholar 

  28. Khanbekov, R.G., Rasulkulov, Kh.M., Virgil'ev,<del> </del>Yu.S., et al., Resistance of Carbon-Carbon Composite Materials to High-Temperature Neutron Irradiation, Neorg. Mater., 1991, vol. 27, no. 12, pp. 2664–2666.

    Google Scholar 

  29. Virgil'ev, Yu.S., Kalyagina, I.P., Vlasov, K.P., and Il'in, V.T., Radiation Resistance of Carbon-Carbon Composite Materials, Neorg. Mater., 1992, vol. 28, no. 1, pp. 66?71.

    Google Scholar 

  30. Lebedev, I.G. and Pokrovskii, A.S., Radiation Testing of Carbon-Carbon Composite Materials, Sb. Tr. GNTs RF NIIAR, 1998, no. 4, pp. 41–53.

  31. Virgil'ev, Yu.S., Irradiation Behavior of Siliconized Graphites, Neorg. Mater., 1997, vol. 33, no. 6, pp. 683–690 [Inorg. Mater.(Engl. Transl.), vol. 33, no. 6, pp. 570-576].

    Google Scholar 

  32. Virgil'ev, Yu.S., Kalyagina, I.P., Rasulkulov, Kh.M., et al., High-Temperature Neutron Irradiation of Carbon Materials, Neorg. Mater., 1997, vol. 33, no. 5, pp. 553–561 [Inorg. Mater.(Engl. Transl.), vol. 33, no. 5, pp. 464-471].

    Google Scholar 

  33. Burtseva, T.A., Bagautdinov, R.M., Chugunov, O.K., et al., The Effect of Neutron Irradiation on the Property Changes in Recrystallized Graphites and Carbon-Carbon Fiber Materials, Mater. Specialist Meet. ICFRM-8, Sendai, 1997.

  34. Burchell, T.D., Eatherly, W.P., Robbins, J.M., and Strizak, J.P., The Effects of Neutron Irradiation on the Structure and Properties of Carbon-Carbon Composite Materials, J. Nucl. Mater., 1992, nos. 191-194, p. 245.

  35. Bonal, J.P., Thiele, B., Tsotridis, G., and Wu, C.H., J. Nucl. Mater., 1994, nos. 212-215, p. 1218.

  36. Virgil'ev, Yu.S., Ponomarev, O.V., and Ponomareva, E.V., Irradiation Behavior of Carbon-Based Composite Materials, Neorg. Mater., 1996, vol. 32, no. 9, pp. 1108–1117 [Inorg. Mater.(Engl. Transl.), vol. 32, no. 9, pp. 971-979].

    Google Scholar 

  37. Virgil'ev, Yu.S. and Kurolenkin, E.I., Structural Carbon Materials for Fusion Reactor Applications and Their Radiation Resistance, Vopr. At. Nauki Tekh., Ser.: Termoyad. Sint., 1992, no. 2, pp. 42–51.

  38. Virgil'ev, Yu.S., Effect of Low-Temperature (50-90?C) Neutron Irradiation on Properties of Structural Graphites, Fiz. Khim. Obrab. Mater., 1993, no. 3, pp. 5–16.

  39. Burtseva, T.A., Chugunov, O.K., Dovguchits, E.F., et al., Resistance of Carbon-Based Materials for the ITER Divertor under Different Radiation Fluxes, Mater. Specialist Meet. ICFRM-5, Clearwater, 1991.

  40. Wu, C.H., Bonal, J.P., Thiele, B., et al., Neutron Irradiation Effects on the Properties of Carbon Materials, J. Nucl. Mater., 1994, nos. 212-215, pp. 416–420.

  41. Virgil'ev, Yu.S., Reaktornyi grafit i ego svoistva (Reactor Graphite and Its Properties), Moscow: TsNIIekonominformtsvetmet, 1990.

    Google Scholar 

  42. Eto, M., Ishyama, S., Ugachi, H., et al., J. Nucl. Mater., 1994, nos. 212-215, p. 1223.

Download references

Author information

Authors and Affiliations

Authors

Rights and permissions

Reprints and permissions

About this article

Cite this article

Virgil'ev, Y.S., Kalyagina, I.P. Carbon–Carbon Composite Materials. Inorganic Materials 40 (Suppl 1), S33–S49 (2004). https://doi.org/10.1023/B:INMA.0000036327.90241.5a

Download citation

  • Issue Date:

  • DOI: https://doi.org/10.1023/B:INMA.0000036327.90241.5a

Keywords

Navigation