Magnesiothermic Reduction Process Applied to the Powder Production of U(Mo) Fissile Particles

被引:4
作者
Champion, Guillaume [1 ]
Allenou, Jerome [1 ]
Pasturel, Mathieu [1 ]
Noel, Henri [1 ]
Charollais, Francois [2 ]
Anselmet, Marie-Christine [2 ]
Iltis, Xaviere [2 ]
Tougait, Olivier [1 ]
机构
[1] Univ Rennes 1, Inst Sci Chim Rennes, UMR 6226, CNRS, F-35042 Rennes, France
[2] CEA, DEN, DEC, F-13108 Cadarache St Paul Lez Du, France
关键词
WT-PERCENT-MO; CENTRIFUGAL ATOMIZATION; MECHANISMS; FUEL;
D O I
10.1002/adem.201200235
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Uranium-molybdenum alloy powders are obtained by a new synthetic route deriving from the Kroll process which avoids a "melting-solidification" step. This alternative process consists in the reduction of uranium dioxide by magnesium in presence of Mo in a sealed Mo crucible heated at temperatures ranging from 750 to 1100 degrees C for dwell periods ranging from 12 to 48 h. An appropriate quenching allows the retention of the high temperature bcc-form gamma-U(Mo). The side products are easily removed by a soaking into a diluted hydrochloric acid solution under sonication. The agglomerates have a typical size in the range 10-200 mu m, with an irregular shape. They display even at the periphery equiaxed grains with homogeneous distribution of Mo. Small closed porosity, which seems to be preferentially located at the grain boundaries corresponds to roughly 2% of the volume fraction.
引用
收藏
页码:257 / 261
页数:5
相关论文
共 19 条
[1]   U-Mo/Al-Si interaction: Influence of Si concentration [J].
Allenou, J. ;
Palancher, H. ;
Iltis, X. ;
Cornen, M. ;
Tougait, O. ;
Tucoulou, R. ;
Welcomme, E. ;
Martin, Ph. ;
Valot, C. ;
Charollais, F. ;
Anselmet, M. C. ;
Lemoine, P. .
JOURNAL OF NUCLEAR MATERIALS, 2010, 399 (2-3) :189-199
[2]  
Allenou J., 2010, French patent application, Patent No. [10 61319, 1061319]
[3]  
Allenou J., 2011, French patent, Patent No. [14 50678, 1450678]
[4]  
CHAMPAGNE B, 1984, POWDER METALL INT, V16, P125
[5]   THE URANIUM-MOLYBDENUM EQUILIBRIUM DIAGRAM BELOW 900-DEGREES-C [J].
DWIGHT, AE .
JOURNAL OF NUCLEAR MATERIALS, 1960, 2 (01) :81-87
[6]  
Ellingham H. J. T., 1944, Chem. Ind, V63, P125, DOI [10.1002/jctb.5000630501, DOI 10.1002/JCTB.5000630501]
[7]   Transmission electron microscopy characterization of irradiated U-7Mo/Al-2Si dispersion fuel [J].
Gan, J. ;
Keiser, D. D., Jr. ;
Wachs, D. M. ;
Robinson, A. B. ;
Miller, B. D. ;
Allen, T. R. .
JOURNAL OF NUCLEAR MATERIALS, 2010, 396 (2-3) :234-239
[8]  
Glaser A., 2005, 27 INT M RED ENR RES
[9]   Jules Horowitz Reactor: a high performance material testing reactor [J].
Iracane, Daniel ;
Chaix, Pascal ;
Alamo, Ana .
COMPTES RENDUS PHYSIQUE, 2008, 9 (3-4) :445-456
[10]   Characterization of U-2 wt% Mo and U-10 wt% Mo alloy powders prepared by centrifugal atomization [J].
Kim, KH ;
Lee, DB ;
Kim, CK ;
Hofman, GE ;
Paik, KW .
JOURNAL OF NUCLEAR MATERIALS, 1997, 245 (2-3) :179-184