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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
2021 ANS Winter Meeting and Technology Expo
November 30–December 3, 2021
Washington, DC|Washington Hilton
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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Nuclear Science and Engineering
November 2021
Nuclear Technology
Fusion Science and Technology
August 2021
Latest News
Inspecting nuclear facilities with unmanned aerial systems
Over the past decade, unmanned aerial systems (UASs), more commonly referred to as drones, have played an increasing role in the day-to-day activities of the energy sector. Applications range from visually inspecting wind turbines, flare stacks, pipelines, and facilities to evaluating vegetation encroachment near power lines. Although the benefits of UASs have been reported in these industries, their use in the nuclear community has only recently been explored. For instance, a drone was sent into a waterbox at a Duke Energy facility to inspect for leaks.1 And at Fukushima Daiichi, a drone was used to conduct a post-accident radiation survey inside Unit 3, and drones are being investigated for use inside the damaged containments.2
Kazunari Katayama, Hiroki Ushida, Hideaki Matsuura, Satoshi Fukada, Minoru Goto, Shigeaki Nakagawa
Fusion Science and Technology | Volume 68 | Number 3 | October 2015 | Pages 662-668
Technical Paper | Proceedings of TOFE-2014 | dx.doi.org/10.13182/FST14-968
Articles are hosted by Taylor and Francis Online.
Tritium production utilizing nuclear reactions by neutron and lithium in a high-temperature gas-cooled reactor is attractive for development of a fusion reactor. From viewpoints of tritium safety and recovery efficiency, tritium confinement is an important issue. It is known that alumina has high resistance for gas permeation. In this study, hydrogen permeation experiments in commercial alumina tubes were conducted and hydrogen permeability, diffusivity and solubility were evaluated. By using obtained data, tritium permeation behavior from an Al2O3-coated Li-compound particle was simulated. Additionally, by using literature data for hydrogen behavior in zirconium, an effect of Zr incorporation into an Al2O3 coating on tritium permeation was discussed. It was indicated that the majority of produced tritium was released through the Al2O3 coating above 500 °C. However, it is expected that total tritium leak is suppressed to below 0.67 % of total tritium produced at 500 °C by incorporating Zr fine particles into the inside of Al2O3 coating, assuming tritium pressure inside particle is kept at the plateau pressure of the Zr hydride generation reaction.
