ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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November 2024
Latest News
MIT’s nuclear professional courses benefit United States—and now Australia too
Some 30 nuclear engineering departments at universities across the United States graduate more than 900 students every year. These young men and women are the present and future of the domestic nuclear industry as it seeks to develop and deploy advanced nuclear energy technologies, grow its footprint on the power grid, and penetrate new markets while continuing to run the existing fleet of reactors reliably and economically.
Catharina Nästrén, Asunción Fernandéz-Carretero, Joseph Somers
Nuclear Technology | Volume 181 | Number 2 | February 2013 | Pages 331-336
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT13-A15787
Articles are hosted by Taylor and Francis Online.
Use of composites of actinide oxides dispersed in a Mo metal matrix is a recent inert matrix fuel concept for the transmutation of Pu and the minor actinides (Np, Am, and Cm). These elements are present in spent nuclear fuel, and their long-term radiotoxicity can be minimized if they are recovered from the fuel and irradiated in dedicated targets in nuclear reactors. The synthesis of such highly radioactive fuels is not simple, and given the high radiotoxicity of Am, the safety of operation of such a process must be examined for production of small-scale analytical batches. Infiltration of americium nitrate into porous PuO2 beads has potential safety bonuses. The beads are produced by a sol-gel external gelation route. Tests have been developed here with CeO2, as a surrogate for PuO2, and have been optimized for both bead production and pelletization of a blend of calcined beads and Mo powder. Addition of carbon to the sol-gel feed solution and its subsequent pyrolysis provides a means to optimize the porosity of the oxide beads. The carbon acts as a pore former. The highest-quality product meeting typical fuel specifications required addition of 20 g/l carbon in the sol-gel feed and calcination of the CeO2 beads at 800°C. Subsequent Mo cermet composites with 20 or 40 vol% of ceramic reached densities in excess of 90% of the theoretical value as is required for nuclear reactor applications. Finally, the step from CeO2 surrogates to (Pu, Am)O2 targets has been made and pellets of excellent quality produced.