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
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.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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Fusion Science and Technology
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Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
M. Nakamichi, J. H. Kim
Fusion Science and Technology | Volume 66 | Number 1 | July-August 2014 | Pages 157-162
Technical Paper | doi.org/10.13182/FST13-745
Articles are hosted by Taylor and Francis Online.
Advanced neutron multipliers with low swelling and high stability at high temperatures are desired for the pebble bed blankets of demonstration fusion power (DEMO) reactors. Beryllium intermetallic compounds (beryllides) such as Be12Ti are the most promising material for this purpose. To fabricate the beryllide pebbles, a new granulation process has been established that combines a plasma sintering method for beryllide synthesis and a rotating electrode method using a plasma-sintered electrode for granulation. In trial granulation examinations, prototypic beryllide pebbles 1 mm in diameter were successfully fabricated. This study describes the results of a crush test and the characterization of the oxidation properties of the prototypic beryllide pebbles compared with those of Be pebbles. The crush test revealed that the prototypic beryllide pebble was more brittle than a Be pebble, and its crush load is one-third that of a Be pebble. The oxidation experiment showed that the weight gain ratios of the prototypic beryllide pebbles were significantly smaller than those of pure Be pebbles. The results confirmed that the prototypic beryllide pebbles have better oxidation resistance than pure Be pebbles.
