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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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
May 2025
Latest News
DTE Energy studying uprate at Fermi-2, considers Fermi-3’s prospects
DTE Energy, the owner of Fermi nuclear power plant in Michigan, is considering an extended uprate for Unit 2 that would increase its 1,100-MW generation capacity by 150 MW.
Andrey Markin, Alexander Gorodetsky, Francesco Scaffidi-Argentina, Heinrich Werle, Chung H. Wu, Andrey Zakharov
Fusion Science and Technology | Volume 38 | Number 3 | November 2000 | Pages 363-368
Technical Paper | Special Issue on Beryllium Technology for Fusion | doi.org/10.13182/FST00-A36151
Articles are hosted by Taylor and Francis Online.
Deuterium trapping in beryllium oxide films irradiated with 400 eV D ions has been studied by Thermal Desorption Spectroscopy (TDS). It has been found that for thermally grown BeO films implanted in the range 300–900 K the total deuterium retention doesn’t depend on irradiation temperature whereas TDS spectra are temperature dependent. For R.T. implantation the deuterium is released in a wide range from 500 to 1100 K. At implantation above 600 K the main portion of retained deuterium is released in a single peak centered at about 1000 K. The similar TDS peak is measured for D/BeO co-deposited layer. In addition we correlate our implantation data on BeO with the relevant data on beryllium metal and carbon. The interrelations between deuterium retention and microstructure are discussed.