Download fulltext HTML
Shornikov, D. P., Tenishev, A. V., Nikitin, S. N., Tarasov, B. A., Starikov, S. V., Efimenko, A. S., Timoshin, I. S., & Matvenov, M. E. (2018). The Study of the Properties of Uranium Dioxide Pellets Depending on the Parameters of Pressing and Sintering. KnE Materials Science, 4(1), 471–479. https://doi.org/10.18502/kms.v4i1.2200

https://doi.org/10.18502/kms.v4i1.2200

statistics

  • 345 Abstract Views
  • 473 PDF Views
  • 0 HTML Views

authors

  • D P Shornikov
    No author data available.
  • A V Tenishev
    No author data available.
  • S N Nikitin
    No author data available.
  • B A Tarasov
    No author data available.
  • S V Starikov
    No author data available.
  • A S Efimenko
    No author data available.
  • I S Timoshin
    No author data available.
  • M E Matvenov
    No author data available.

Published Date

  • May 6, 2018

The Study of the Properties of Uranium Dioxide Pellets Depending on the Parameters of Pressing and Sintering

KnE Materials Science / 15th International School-Conference "New Materials – Materials of Innovative Energy" (MIE) / Pages 471–479

Abstract

The paper presents dilatometric research of uranium dioxide pellets, fabricated by compaction at different pressure values. Temperature observed at sintering start is determined and it is pointed out that this temperature doesn’t depend on compaction pressure.


Keywords: uranium dioxide, compaction, sintering, dilatometry, shrink curves, geometric density, pycnometric density.

References
[1] Advanced fuel pellet materials and designs for water cooled reactors IAEA-TECDOC- 1416, IAEA, Vienna, 2004.


[2] Kotelnikov R.B., Bashlykov S.N., Kashtanov A.I.. Menshikova T.S. High-temperature nuclear fuel Atomizdat, 1978, 432 p.


[3] Majorov A.A., Braverman I.B. The technology of obtaining powders of ceramic uranium dioxide Energoatomizdat 1985, 127 p.


[4] Baranov, V.G., Devyatko, Yu.N., Tenishev, A.V., Khlunov, A.V., Khomyakov, O.V. Sintering of oxide nuclear fuel: Plastic flow mechanism. (2013) Journal of Nuclear Materials 432 (1-3) PP. 52 - 56 http://dx.doi.org/10.1016/j.jnucmat.2012.07.050


[5] Wilkinson D.S., Ashby M.F. Pressure sintering by power law creep Acta Metallurgica. 1975. Vol. 23. Is. 11. P. 1277-1285


[6] Baranov, V.G., Kuzmin, R.S., Tenishev, A.V., Khlunov, A.V., Ivanov, A.V., Petrov, I.V., Timoshin, I.S. Sintering parameters for uranium-gadolinium oxide fuel pellets. (2012) Atomic Energy 112 (4) PP. 303 - 306 http://dx.doi.org/10.1007/s10512-012- 9561-2


[7] Baranov, V.G., Kuzmin, R.S., Tenishev, A.V., Khlunov, A.V., Ivanov, A.V., Petrov, I.V., Timoshin, I.S. Sintering particulars of pelletized oxide nuclear fuel. (2011) Atomic Energy 110 (3) PP. 172 - 177 http://dx.doi.org/10.1007/s10512-011-9407-3