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Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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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Latest News
Can hydrogen be the transportation fuel in an otherwise nuclear economy?
Let’s face it: The global economy should be powered primarily by nuclear power. And it probably will by the end of this century, with a still-significant assist from renewables and hydro. Once nuclear systems are dominant, the costs come down to where gas is now; and when carbon emissions are reduced to a small portion of their present state, it will become obvious that most other sources are only good in niche settings. I mean, why use small modular reactors to load-follow when they can just produce that power instead of buffering it?
A. Jankowiak, F. Jorion, C. Maillard, L. Donnet
Nuclear Science and Engineering | Volume 160 | Number 3 | November 2008 | Pages 378-384
Technical Paper | doi.org/10.13182/NSE160-378
Articles are hosted by Taylor and Francis Online.
This study describes the preparation and characterization of Pu0.5Am0.5O2-x-MgO ceramic/ceramic (cercer) composites with 20 and 30 vol% of Pu0.5Am0.5O2-x. The sintered materials demonstrated very different reduction behavior when exposed to a reducing sintering cycle. The composites were studied by combined X-ray diffraction (XRD) and oxygen-to-metal ratio measurements and exhibited various amounts of body-centered-cubic (bcc) and face-centered-cubic (fcc) phases corresponding to different reduction states of the mixed actinide oxide. The fcc phases correspond to a near stoichiometry phase while the bcc phases are attributed to most reduced phases, which demonstrate a greater similarity with the Am2O3 bcc phase. The XRD results suggest a reduction of Am prior to Pu, which explains this greater similarity. In addition, the 30 vol% composite contains 65 wt% of the bcc phase while the 20 vol% composite exhibits only 29 wt%. This result can be explained by the percolation theory when applied to the oxygen diffusivity and indicates that a threshold value for Pu0.5Am0.5O2-x content in the cercer composite exists where the reduction of the mixed oxide significantly increases.