TY - GEN
T1 - Optimization of sintering parameters for nitride transmutation fuels
AU - Dunwoody, John T.
AU - Stanek, Christopher R.
AU - McClellan, Kenneth J.
AU - Voit, Stewart L.
AU - Hartmann, Thomas
AU - Wheeler, Kirk
AU - Parra, Manuel
AU - Peralta, Pedro
PY - 2006
Y1 - 2006
N2 - One mission of the Advanced Fuel Cycle Initiative (AFCI) is to develop transmutation fuels (i.e. fuels capable of having their transuranic elements transmuted to a shorter-lived isotopes) in order to close the nuclear fuel cycle, thereby reducing: the U.S. inventory of civilian plutonium, the waste stored in geologic repositories, and the cost of nuclear waste management. Actinide mononitrides are potential transmutation fuel materials due to favorable properties such as high melting point, excellent thermal conductivity, high fissile density, suitability towards reprocessing, and good radiation tolerance1. In order to avoid the difficulties of working with actinide bearing materials, we have performed a processing study on ZrN. ZrN is isostructural (i.e. NaCl structure) with actinide nitrides, and is therefore a good surrogate compound. Furthermore, ZrN is a diluent in so-called "non-fertile" fuels, i.e. containing no uranium. The effects of sintering were investigated by varying both the sintering atmosphere and temperature in order to determine the effect on important properties such as density and nitrogen stoichiometry. The density and stoichiometry values were then compared to hardness and microstrucrure on similar samples. The results of these studies are presented in the context of the various issues associated with the design and fabrication of actinide-bearing nitride fuel forms.
AB - One mission of the Advanced Fuel Cycle Initiative (AFCI) is to develop transmutation fuels (i.e. fuels capable of having their transuranic elements transmuted to a shorter-lived isotopes) in order to close the nuclear fuel cycle, thereby reducing: the U.S. inventory of civilian plutonium, the waste stored in geologic repositories, and the cost of nuclear waste management. Actinide mononitrides are potential transmutation fuel materials due to favorable properties such as high melting point, excellent thermal conductivity, high fissile density, suitability towards reprocessing, and good radiation tolerance1. In order to avoid the difficulties of working with actinide bearing materials, we have performed a processing study on ZrN. ZrN is isostructural (i.e. NaCl structure) with actinide nitrides, and is therefore a good surrogate compound. Furthermore, ZrN is a diluent in so-called "non-fertile" fuels, i.e. containing no uranium. The effects of sintering were investigated by varying both the sintering atmosphere and temperature in order to determine the effect on important properties such as density and nitrogen stoichiometry. The density and stoichiometry values were then compared to hardness and microstrucrure on similar samples. The results of these studies are presented in the context of the various issues associated with the design and fabrication of actinide-bearing nitride fuel forms.
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M3 - Conference contribution
AN - SCOPUS:33845933845
SN - 0470080558
SN - 9780470080559
T3 - Ceramic Engineering and Science Proceedings
SP - 29
EP - 38
BT - Ceramics in Nuclear and Alternative Energy Applications - A Collection of Papers Presented at the 30th International Conference on Advanced Ceramics and Composites
T2 - Ceramics in Nuclear and Alternative Energy Applications - 30th International Conference on Advanced Ceramics and Composites
Y2 - 22 January 2006 through 27 January 2006
ER -