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Effect of Neutron Irradiation on Properties of Recrystallized Graphite

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Inorganic Materials Aims and scope

Abstract

Data are presented on the properties of high-density recrystallized graphites manufactured by simultaneously exposing graphite blocks to high temperatures and pressures, and their behavior under neutron irradiation is examined.

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REFERENCES

  1. Shipkov, N.N., Kostikov, V.I., Demin, A.V., and Neproshin, E.M., Rekristallizovannyi grafit (Recrystallized Graphite), Moscow: Metallurgiya, 1979.

    Google Scholar 

  2. Ostrovskii, V.S., Virgil'ev, Yu.S., Kostikov, V.I., and Shipkov, N.N., Iskusstvennyi grafit (Synthetic Graphite), Moscow: Metallurgiya, 1986.

    Google Scholar 

  3. Virgil'ev, Yu.S. and Makarchenko, V.G., Irradiation Behavior of Graphite after Thermomechanical Processing, Izv. Akad. Nauk SSSR, Neorg. Mater., 1983, vol. 19, no. 8, pp. 1314-1318.

    Google Scholar 

  4. Virgil'ev, Yu.S., Criterion for the Performance of Carbon Materials, Khim. Tverd. Topl. (Moscow), 2001, no. 5, pp. 68-77.

  5. Virgil'ev, Yu.S., Porosity and Some Other Physical Properties of Structural Graphite, Khim. Tverd. Topl. (Moscow), 1973, no. 5, p. 102.

  6. Normy rascheta prochnosti tipovykh uzlov iz grafita uran-grafitovykh kanal'nykh reaktorov, NGR-01-90 (Strength Calculations of Standard Graphite Units of Graphite-Uranium Channel Reactors, NGR-01-90) Moscow: NIKIET, IAE, UPI, NIIGrafit, 1990.

  7. Vyatkin, S.E., Deev, A.N., Nagornyi, V.G., et al., Yadernyi grafit (Nuclear Graphite), Moscow: Atomizdat, 1967.

    Google Scholar 

  8. 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. 42-52.

  9. Burtseva, T.A., Mazul, I.V., Kostikov, V.I., et al., The Structural Properties and Behavior of Modified Boron and Titanium Doped Graphites under Different Radiation Fluxes, Mater. ICFRM-8 Spec. Meet., Sendai, 1997.

  10. Svoistva konstruktsionnykh materialov na osnove uglerodov: Spravochnik (Properties of Carbon-Based Structural Materials: A Handbook), Sosedov, V.P., Ed., Moscow: Metallurgiya, 1975.

    Google Scholar 

  11. Virgil'ev, Yu.S., Structural Carbon Materials for Fusion Reactor Applications and Their Radiation Resistance, Fiz. Khim. Obrab. Mater., 1993, no. 2, pp. 5-21.

  12. 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 

  13. Virgil'ev, Yu.S., Chugunova, T.K., and Rakcheeva, V.I., Radiation Resistance of Recrystallized Graphite, Fiz. Khim. Obrab. Mater., 1992, no. 1, p. 5.

  14. 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. ICFRM-8 Spec. Meet., Sendai, 1997.

  15. Lebedev, I.G. and Pokrovskii, A.S., Properties of Reactor-Irradiated Recrystallized Graphite, Sb. Tr. Naucno-Issled. Inst. At. Reakt., 1999, no. 1, pp. 65-71.

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

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

    Google Scholar 

  18. Kurolenkin, E.I. and Virgil'ev, Yu.S., Supramolecular Structure of Carbon Materials, Khim. Tverd. Topl. (Moscow), 1980, no. 5, pp. 77-86.

  19. Virgil'ev, Yu.S., Structural Carbon Materials for Thermonuclear Reactors, Neorg. Mater., 1994, vol. 30, no. 7, pp. 903-916 [Inorg. Mater. (Engl. Transl.), vol. 30, no. 7, pp. 838-849].

    Google Scholar 

  20. Virgil'ev, Yu.S., Effect of Low-Temperature (320-360 K) Neutron Irradiation on the Properties of Structural Graphites, Fiz. Khim. Obrab. Mater., 1993, no. 3, pp. 5-16.

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  1. Research Institute of Structural Graphite Materials, Elektrodnaya ul. 2, Moscow, 111524, Russia

    Yu. S. Virgil'ev

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  1. Yu. S. Virgil'ev
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Virgil'ev, Y.S. Effect of Neutron Irradiation on Properties of Recrystallized Graphite. Inorganic Materials 40, 468–476 (2004). https://doi.org/10.1023/B:INMA.0000027592.88573.51

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  • DOI: https://doi.org/10.1023/B:INMA.0000027592.88573.51

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