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Atomic Energy

, Volume 125, Issue 3, pp 194–197 | Cite as

Investigation of the Character of Stored-Energy Release from Graphite Irradiated at High Temperature

  • E. P. Belan
  • D. V. Khar’kov
  • A. V. Avdonin
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The results of an investigation of the stored energy in GR-280 graphite irradiated at 560°C to neutron fluence ~3·1026 m–2 are presented. The measurements were performed by means of differential scanning calorimetry with constant heating rate 20°C/min. The release of the stored energy reaches a maximum at annealing temperature 1100°C. The maximum output is equal to 0.34–0.48 J/(g·°C). The total stored energy released in the annealing temperature range 560–1300°C does not exceed 183 J/g. A kinetic analysis of the spectrum of the stored energy was performed. This analysis established that increasing the radiation temperature from 450 to 560°C results in almost complete vanishing of individual vacancies, redistribution of the migration of di-vacancies, and evolution of a cluster structure upon post-radiation annealing in the range 560–1300°C in the direction of processes with lower activation energy.

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References

  1. 1.
    T. Burchell, “Irradiation damage in graphite – from the nano- to the mille-metric scale,” Techn. Meeting on High-Temperature Qualification of High-Temperature Gas Cooled Materials, IAEA, Vienna (2014).Google Scholar
  2. 2.
    N. Gallego, “A review of stored energy release of irradiated graphite,” Milestone Report on the Workshop on HTGR Graphite Stored Energy Release, ORNL/TM-2011/378.Google Scholar
  3. 3.
    A. S. Pokrovsky, E. P. Belan, and D. V. Kharkov, “Stored energy in graphite irradiated to high neutron fluences,” Fund. Issled, No. 5-1, 130–136 (2015).Google Scholar
  4. 4.
    A. S. Pokrovsk, E. P. Belan, and A. V. Avdonin, “Changes in the thermophysical properties of irradiated reactor graphite during high-temperature annealing,” in: Collection of Works of GNTs NIIAR (2015), Iss. 1, pp. 3–10.Google Scholar
  5. 5.
    S. E. Vyatkin, A. E. Deev, V. G. Nagornyi, et al., Nuclear Graphite, Atomizdat, Moscow (1967).Google Scholar
  6. 6.
    R. Nightingale, Nuclear Graphite, Academic Press, London (1962).Google Scholar
  7. 7.
    T. Iwata, “Fine structure of Wigner energy release spectrum in neutron irradiated graphite,” J. Nucl. Mater., 133–134, 361–364 (1985).CrossRefGoogle Scholar
  8. 8.
    E. Asari, M. Kitajima, K. Nakamura, and T. Kawabe, “Thermal relaxation of ion-irradiation damage in graphite,” Phys. Rev., 47, 143–148 (1993).MathSciNetCrossRefGoogle Scholar
  9. 9.
    A. El-Barbary, First Principles Characterization of Defects in Irradiated Graphitic Materials: A Thesis Submitted Towards Fulfilment of the Requirement for the Degree of Doctor of Philosophy, Sussex (2005).Google Scholar
  10. 10.
    R. Telling and M. Heggie, “Radiation defects in graphite,” Philos. Magaz., 87, 797–846 (2007).CrossRefGoogle Scholar

Copyright information

© Springer Science+Business Media, LLC, part of Springer Nature 2018

Authors and Affiliations

  • E. P. Belan
    • 1
  • D. V. Khar’kov
    • 1
  • A. V. Avdonin
    • 1
  1. 1.State Science Center – Research Institute for Atomic Reactors (GNTs NIIAR)DimitrovgradRussia

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