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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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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What’s in your Dubai chocolate? Nuclear scientists test pistachios for toxins
For the uninitiated, Dubai chocolate is a candy bar filled with pistachio and tahini cream and crispy pastry recently popularized by social media influencers. While it’s easy to dismiss as a viral craze now past its peak, the nutty green confection has spiked global pistachio demand, and growers and processors are ramping up production. That means more pistachios need to be tested for aflatoxins—a byproduct of a common crop mold.
C. J. Orth
Nuclear Science and Engineering | Volume 9 | Number 4 | April 1961 | Pages 417-420
Technical Paper | doi.org/10.13182/NSE61-A25905
Articles are hosted by Taylor and Francis Online.
Measurements were made of the diffusion losses of lanthanide and actinide elements from graphite at temperatures from 1600 to 2600°C. In the lanthanide series, a close correlation was observed between the diffusion rates from graphite and the boiling points of the metals. Where boiling point measurements permit comparison, a similar correlation was also noted for the actinides. The most volatile of these elements are the ones for which lower oxidation states can be attained chemically [Sm(II), Eu(II), Yb(II), and possibly Am(II)]. Conversely, those elements which exhibit oxidation states higher than (III) show high-temperature stability in graphite. Although the diffusion loss of uranium is not negligible above 2100°C, no loss was detected from a small graphite pin heated for four hours at 2050°C; under the same conditions, about 50% of the plutonium was lost. The possible significance of these measurements to high-temperature reactor design is discussed briefly.