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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
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
Latest News
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.
C. Fagan, M. Sharpe, W. T. Shmayda, W. U. Schröder
Fusion Science and Technology | Volume 76 | Number 4 | May 2020 | Pages 424-429
Technical Paper | doi.org/10.1080/15361055.2020.1714409
Articles are hosted by Taylor and Francis Online.
The effect of a thin alumina coating on stainless steel 316 (SS316) samples on tritium adsorption and transport are reported. Compact films of alumina were produced on the surfaces of pristine SS316 samples using an atomic layer deposition (ALD) technique. Subsequently, these samples were exposed for 24 h to a deuterium-tritium gas mixture (PT = 0.5 atm, 25°C). A combination of methods including selective etching and programmed thermal desorption were employed to assess both the depth profile of the tritium concentration in the sample and the total quantity of tritium absorbed, respectively. Tritium was quantitatively determined through the measurement of beta radioactivity using liquid-scintillation counting techniques. Data suggest that SS316 with a thin film of alumina reduces the total tritium uptake by ~25% relative to uncoated samples. Importantly, such films appear to reduce, by a factor of 200, tritium diffusion into SS316 and therefore constitute an effective barrier against tritium transport. This observation is of practical importance for tritium and, generally, reactive gas handling.