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UMo/Al nuclear fuel plate behavior under thermal treatment (425-550°C)

  • H. Palancher (a1), A. Bonnin (a1) (a2), C.V. Colin (a3), V. Nassif (a3), V. Honkimäki (a2), R. Jungwirth (a4), C. Ritter (a5), G. Champion (a1) and Y. Calzavara (a5)...
Abstract

Nuclear fuel plates based on a γU-Mo/Al mixture are proposed for research reactors. In this work their thermal behavior in the [425; 550°C] temperature range has been studied mainly by neutron and high energy X-ray diffraction. Even if complementary studies will be necessary, the kinetics of first the growth of the interaction layer between γU-Mo and Al and second of the γU-Mo destabilization have been accurately measured. This basic work should be helpful for defining manufacturing conditions for fuel plates with optimized composition.

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Corresponding author
a) Author to whom correspondence should be addressed. Electronic email: herve.palancher@cea.fr
References
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Powder Diffraction
  • ISSN: 0885-7156
  • EISSN: 1945-7413
  • URL: /core/journals/powder-diffraction
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