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

Published online by Cambridge University Press:  14 November 2013

H. Palancher ,
A. Bonnin ,
C.V. Colin ,
V. Nassif ,
V. Honkimäki ,
R. Jungwirth ,
C. Ritter ,
G. Champion  and
Y. Calzavara
H. Palancher*
Affiliation:
CEA, DEN, DEC, Cadarache, F13108 Saint Paul lez Durance, France
A. Bonnin
Affiliation:
CEA, DEN, DEC, Cadarache, F13108 Saint Paul lez Durance, France ESRF, BP 220, F38043 Grenoble Cedex, France
C.V. Colin
Affiliation:
Institut Néel, CNRS et Université Joseph Fourier, BP 166, 38042 Grenoble Cedex 9, France
V. Nassif
Affiliation:
Institut Néel, CNRS et Université Joseph Fourier, BP 166, 38042 Grenoble Cedex 9, France
V. Honkimäki
Affiliation:
ESRF, BP 220, F38043 Grenoble Cedex, France
R. Jungwirth
Affiliation:
Forschungsneutronenquelle Heinz Maier-Leibnitz (FRM II), Technische Universität München, D-85747 Garching bei München, Germany
C. Ritter
Affiliation:
ILL, BP 156, 38042 Grenoble Cedex 9, France
G. Champion
Affiliation:
CEA, DEN, DEC, Cadarache, F13108 Saint Paul lez Durance, France
Y. Calzavara
Affiliation:
ILL, BP 156, 38042 Grenoble Cedex 9, France
*
a) Author to whom correspondence should be addressed. Electronic email: herve.palancher@cea.fr
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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.

Keywords

neutron diffractionsynchrotron X-ray diffractionin-situphase analysisnuclear fuels
Type
Technical Articles
Information
Powder Diffraction , Volume 28 , Supplement S2 , September 2013 , pp. S371 - S393
Copyright
Copyright © International Centre for Diffraction Data 2013 

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References

Bonnin, A., Palancher, H., Honkimäki, V., Tucoulou, R., Calzavara, Y., Colin, C. V., Bérar, J-F., Boudet, N., Rouquette, H., Raynal, J., Valot, C. and Rodriguez-Carvajal, J. (2011). “UMo/Al nuclear fuel quantitative analysis via high energy X-ray diffraction,” Z. Kristallogr. (Proceedings EPDIC 2010) 2011, 29–34.Google Scholar
Champion, G., Belin, R., Palancher, H., Iltis, X., Rouquette, H., Pasturel, M., Demange, V., Castany, P., Dorcet, V. and Tougait, O. (2012). “Développement de méthodes de caractérisation sur poudres U(Mo), “ Proceedings of the STP conference 2012, Toulouse (France)Google Scholar
Dwight, A. E. (1960). “The uranium -molybdenum equilibrium diagram below 900°C,” J. Nucl. Mater. 2 81–89.Google Scholar
Gan, J., Keiser, D. D. Jr., Miller, B. D., Wachs, D. M., Allen, T. R., Kirk, M., Rest, J. (2011). “Microstructure of RERTR DU-alloys irradiated with krypton ions up to 100 dpa,” J. Nucl. Mater. 411, 174–180.Google Scholar
Jungwirth, R., Palancher, H., Bonnin, A., Bertrand-Drira, C., Borca, C., Honkimäki, V., Jarousse, C., Stepnik, B., Park, S. H., Iltis, X., Schmahl, W. and Petry, W. (2013) “Microstructure of as-fabricated UMo/Al(Si) plates prepared with ground and atomized powder,” J. Nucl. Mater. 438, 246–260.Google Scholar
Kapusta, B., Sainte-Catherine, C., Averty, X., Scibetta, M., Decroix, G. M., Rommens, M. (2003). Proceedings of the 9th IGORR conference, Sydney, Australia, March 24-28, 2003.Google Scholar
Keiser, D. D. Jr., Jue, J-F., Woolstenhulme, N. E. and Ewh, A. (2011). “Microstructural characterization of U–7Mo/Al–Si alloy matrix dispersion fuel plates fabricated at 500°C,” J. Nucl. Mater. 419, 226–234.Google Scholar
Lee, J.-S., Lee, C.-H., Kim, K. H. and Em, V. (2002). “Study of decomposition and reactions with aluminum matrix of dispersed atomized U-10 wt% Mo alloy,” J. Nucl. Mater. 306, 147–152.Google Scholar
Massalski, T. B. (1990). Binary Alloy Phase Diagrams (ASM International, Materials Park, OH), 2nd Ed. Google Scholar
Mirandou, M. I., Balart, S. N., Ortiz, M., Granovsky, M. S. (2003). “Characterization of the reaction layer in U-7wt%Mo/Al diffusion couples,” J. Nucl. Mater. 323, 29–35.Google Scholar
Palancher, H., Martin, P., Nassif, V., Tucoulou, R., Proux, O., Hazemann, J-L., Tougait, O., Lahéra, E., Mazaudier, F., Valot, C. and Dubois, S. (2007). “Evidence for the presence of U-Mo-Al ternary compounds in the U-Mo/Al interaction layer grown by thermal annealing: A coupled micro X-ray diffraction and micro X-ray absorption spectroscopy study,” J. Appl. Crystallogr. 40, 1064–1075.Google Scholar
Palancher, H., Tucoulou, R., Bleuet, P., Bonnin, A., Welcomme, E. and Cloetens, P. (2011). “Hard X-ray diffraction scanning tomography with sub-micrometre spatial resolution: application to an annealed γ-U0.85Mo0.15 particle,” J. Appl. Crystallogr. 44, 1111–1119.Google Scholar
Palancher, H., Bonnin, A., Honkimäki, V., Cloetens, P., Suhonnen, H., Zweifel, T., Tucoulou, R., Rack, A. and Voltolini, M. (2012a). “Coating thickness determination in highly absorbent core–shell systems,” J. Appl. Crystallogr. 45, 906–913.Google Scholar
Palancher, H., Bonnin, A., Honkimäki, V., Buslaps, T., Grasse, M., Stepnick, B., Zweifel, T. (2012b). “Quantitative crystallographic analysis of as-fabricated full size UMo/Al(Si) nuclear fuel plates,” J. Alloys Compd. 527, 53–65.Google Scholar
Palancher, H., Iltis, X., Bonnin, A., Charollais, F., Lemoine, P., Van Den Berghe, S., Leenaers, A., Koonen, E., Stepnick, B., Jarousse, C., Calzavara, Y. and Guyon, H. (2012c). “LEONIDAS E-FUTURE-II: Characteristics of the fresh fuel plates,” Proceedings of the 2012 RRFM Conference, Prague, Czech Republic, march 18-22, 2012, 709–718.Google Scholar
Park, J. M, Ryu, H. J., Oh, S. J., Lee, D. B., Kim, C. K., Kim, Y. S., Hofman, G. L. (2008). “Effect of Si and Zr on the interdiffusion of U–Mo alloy and Al,” J. Nucl. Mater. 374, 422–430.Google Scholar
Park, J. M., Ryu, H. J., Kim, K. H., Lee, D. B, Lee, Y. S., Lee, J. S., Seong, B. S., Kim, C. K. and Cornen, M. (2010). “Neutron diffraction analyses of U–(6–10 wt.%)Mo alloy powders fabricated by centrifugal atomization,” J. Nucl. Mater. 397, 27–30.Google Scholar
Perez, E., Keiser, D. D. Jr., and Sohn, Y. H. (2011). “Phase Constituents and Microstructure of Interaction Layer Formed in U-Mo Alloys vs Al Diffusion Couples Annealed at 873 K (600 A degrees C),” Metall. Mater. Trans. A, 42, 3071–3083.Google Scholar
Tangri, K., Williams, G. I. (1961). “Metastable phases in the uranium-molybdenum system and their origin,” J. Nucl. Mater. 2, 226–233.Google Scholar
Yao, B., Perez, E., Keiser, D. D. Jr., Jue, J.-F., Clark, C. R., Woolstenhulme, N., Sohn, Y. (2011). “Microstructure characterization of as-fabricated and 475 °C annealed U–7 wt.% Mo dispersion fuel in Al–Si alloy matrix,” J. Alloys Compd. 509, 9487–9496.CrossRefGoogle Scholar