Hostname: page-component-586b7cd67f-vdxz6 Total loading time: 0 Render date: 2024-11-28T05:24:09.955Z Has data issue: false hasContentIssue false
  • English
  • Français

Spark Plasma Sintering of Fuel Cermets for Nuclear Reactor Applications

Published online by Cambridge University Press:  27 February 2012

Yang Zhong ,
Robert C. O’Brien ,
Steven D. Howe ,
Nathan D. Jerred ,
Kristopher Schwinn ,
Laura Sudderth  and
Joshua Hundley
Yang Zhong
Affiliation:
Center for Space Nuclear Research, Idaho National Laboratory, ID 83415, U.S.A. Department of Chemical, Materials and Biomolecular Engineering, University of Connecticut, CT 06269, U.S.A.
Robert C. O’Brien
Affiliation:
Center for Space Nuclear Research, Idaho National Laboratory, ID 83415, U.S.A.
Steven D. Howe
Affiliation:
Center for Space Nuclear Research, Idaho National Laboratory, ID 83415, U.S.A.
Nathan D. Jerred
Affiliation:
Center for Space Nuclear Research, Idaho National Laboratory, ID 83415, U.S.A.
Kristopher Schwinn
Affiliation:
Center for Space Nuclear Research, Idaho National Laboratory, ID 83415, U.S.A.
Laura Sudderth
Affiliation:
Center for Space Nuclear Research, Idaho National Laboratory, ID 83415, U.S.A.
Joshua Hundley
Affiliation:
Center for Space Nuclear Research, Idaho National Laboratory, ID 83415, U.S.A.
Get access

Abstract

The feasibility of the fabrication of tungsten based nuclear fuel cermets via Spark Plasma Sintering (SPS) is investigated in this work. CeO2 is used to simulate fuel loadings of UO2 or Mixed-Oxide (MOX) fuels within tungsten-based cermets due to the similar properties of these materials. This study shows that after a short time sintering, greater than 90 % density can be achieved, which is suitable to possess good strength as well as the ability to contain fission products. The mechanical properties and the densities of the samples are also investigated as functions of the applied pressures during the sintering.

Keywords

sinteringnuclear materialsdensification
Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 1383: Symposium A – Material Challenges in Current and Future Nuclear Technologies , 2012 , mrsf11-1383-a01-08
Copyright
Copyright © Materials Research Society 2012

Access options

Get access to the full version of this content by using one of the access options below. (Log in options will check for institutional or personal access. Content may require purchase if you do not have access.)

References

REFERENCES

1. U.S Energy Information Administration, Annual Energy Review (2011).Google Scholar
2. Burkes, D. E., Wachs, D.M., Warner, J.E. and Howe, S.D., Proceedings of Space Nuclear Conference 2007, Paper # 2027 (2007).Google Scholar
3. Wang, X., Xie, Y., Guo, H. and Van der Biest, O., Rare Metals 25 246 (2006).Google Scholar
4. O’Brien, R.C., Ambrosi, R.M., Bannister, N.P., Howe, S.D. and Atkinson, H.V., Journal of Nuclear Materials, 393 108 (2009).Google Scholar
5. Rosinski, M., Fortuna, E., Michalski, A., Pakiela, Z., Kurzydlowski, K.J., Fus. Eng. Des. 82 2621 (2007).Google Scholar
6. Zhang, J., Wang, L., Jiang, W., Chen, L., Mater. Sci. Eng. A 487 137 (2008)Google Scholar
7. Kothari, N.C., Journal of Less-Common Metals 5 140 (1963).Google Scholar