doi:10.1016/j.enconman.2006.02.011
Copyright © 2006 Elsevier Ltd All rights reserved.
Properties of cermet fuels for minor actinides transmutation in ADS
References and further reading may be available for this article. To view references and further reading you must
purchase this article.
D. Haasa,
,
, A. Fernandeza, C. Nästrena, D. Staicua, J. Somersa, W. Maschekb and X. Chenb
aEuropean Commission, Joint Research Centre, Institute for Transuranium Elements, Herrmann von Helmholzplatz 1, Postfach 2340, 76125 Karlsruhe, Germany
bForschungszentrum Karlsruhe, Herrmann von Helmholzplatz 1, Postfach 3640, 76021 Karlsruhe, Germany
Available online 27 March 2006.
Abstract
The sub-critical Accelerator Driven System (ADS) is now being considered as a potential means to burn long-lived transuranium nuclides. The preferred fuel for such a fast neutron reactor is uranium-free, highly enriched with plutonium and minor actinides. Requirements for ADS transmuter fuels are linked with the core design and safety parameters, the fuel properties and the ease of reprocessing. This study concerns the properties of metals as matrices, with the particular case of Mo. To improve the neutronic characteristics, enriched molybdenum (Mo-92) is required. To overcome the high enrichment cost, it is proposed to recover the matrix by pellet dissolution, and to recycle it for further use. Irradiation programmes are also planned to examine the in-reactor properties of the material. Based on the current status of the research, the results are promising, but irradiation results are still missing.
Keywords: Transmutation; Fuel; Sub-critical reactor; CERMET
Fig. 1. Axial temperature distribution in inner fuel ring of the 800 MWth ADS.
Fig. 2. UTOC transient: power and reactivity history.
Fig. 3. UTOC transient: temperature development for fuel, clad and coolant.
Fig. 4. Visual aspect of an Am0.244Pu0.756O2−x – Mo pellet. The ceramic phase represents 30% in volume.
Fig. 5. Modeled microstructure of the CERMET: Boolean distribution of spheres with overlap, the volume fraction of inclusions is 30%.
Fig. 6. Thermal conductivity of the CERMET fuel (Pu, Am)O2 – Mo for different volume fractions of inclusions.
Fig. 7. X-ray diffraction of CeO2 beads recovered after dissolution of a MO-CeO2 CERMET pellet.
Table 1.
Typical safety parameters for an 800 MWth ADT with CERMET fuel (Mo-nat and Mo-92)


Corresponding author. Tel.: +49 7247 951 367; fax: +49 7247 951 599.