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Effect of Americium and Simulated Fission Products Addition on Oxygen Potential of Uranium-Plutonium Mixed Oxide Fuels

Published online by Cambridge University Press:  31 January 2011

Kosuke Tanaka ,
Masahiko Osaka ,
Ken Kurosaki ,
Hiroaki Muta ,
Masayoshi Uno  and
Shinsuke Yamanaka
Kosuke Tanaka
Affiliation:
[email protected], Japan Atomic Energy Agency, Ibaraki, Japan
Masahiko Osaka
Affiliation:
[email protected], Japan Atomic Energy Agency, 4002 Narita-cho, Oarai-machi, Higashiibaraki-gun, Ibaraki, 311-1393, Japan
Ken Kurosaki
Affiliation:
[email protected], Osaka University, 2-1 Yamadaoka, Suita, 565-0871, Japan
Hiroaki Muta
Affiliation:
[email protected], Osaka University, Suita, Japan
Masayoshi Uno
Affiliation:
[email protected], University of Fukui, Fukui, Japan
Shinsuke Yamanaka
Affiliation:
[email protected], Osaka University, Suita, Japan
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Abstract

The oxygen potentials at 1273 K of mixed oxide (MOX) fuels with Am and 26 kinds of fission product elements (FPs), simulating low-decontaminated MOX fuel and high burn-up of up to 250 GWd/t, have been measured by using thermogravimetric analysis (TGA). The oxygen potentials for simulated low-decontaminated MOX fuels were higher than the fuels without FPs and increased with increasing simulated burn-up.

Keywords

actinideoxidethermogravimetric analysis (TGA)
Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 1215: Symposium V – Materials Research Needs to Advance Nuclear Energy , 2009 , 1215-V12-04
Copyright
Copyright © Materials Research Society 2010

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References

1. Namekawa, T. et al. , Proc. Int. Conf. GLOBAL 2005, Tsukuba, Japan, Oct. 9-13, 2005, paper No. 424.Google Scholar
2. Kleykamp, H. J. Nucl. Mater., 131, 229(1985).Google Scholar
3.D. Olander, R. Fundamental Aspects of Nuclear Reactor Fuel Elements, TID-26711-P1, 1970.Google Scholar
4. Yuda, R. K., and Une, , J. Nucl. Mater. 178, 195(1991).Google Scholar
5. Miwa, S. et al. , Recent Advances in Actinide Science, Manchester, July 4-8, 2005, eds. May, I. Bryan, N. D. and Alvarez, R. RSC Publishing: pp. 400-402, 2006.Google Scholar
6. Chikalla, T. D. and Eyring, L. Inorg, J.. Nucl. Chem. 29, 2281(1967).Google Scholar
7. Bartscher, W. and Sari, C. J. Nucl. Mater. 118, 220(1983).Google Scholar
8. Osaka, M. et al. , J. Alloys Com., 397, 110(2005).Google Scholar
9. Osaka, M. et al. , J. Alloys Com., 428, 355(2007).Google Scholar
10. Kato, M. et al. , J. Nucl. Mater., 385, 419(2009).Google Scholar
11. Une, K. and Oguma, M. J. Nucl. Sci. Technol., 20, 844(1983)Google Scholar
12. Woodley, R.E. J. Nucl. Mater., 74, 290(1978)Google Scholar
13. Yoshimochi, H. et al. , J. Nucl. Sci. Technol. 41, 850(2004).Google Scholar
14. Lucta, P.G. et al. , J. Nucl. Mater., 188, 198(1992).Google Scholar
15. Une, K. and Oguma, M. J. Nucl. Mater., 131, 88(1985).Google Scholar
16. Ishimoto, S. et al. , J. Nucl. Sci. Technol., 31, 796(1994).Google Scholar