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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.
2020 ANS Virtual Winter Meeting
November 16–19, 2020
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Nuclear Science and Engineering
Fusion Science and Technology
Nuclear in K-12 education: Overview of ANS toolkit and reflections from educators
A free webinar today from 3:00 p.m.-4:30 p.m. (EDT) will look at the resources that the American Nuclear Society has developed with Discovery Education and the Department of Energy’s Office of Nuclear Energy to help K-12 educators teach nuclear science and technology.
The webinar will begin with an overview of the resources, followed by reflections and commentary from three educators of various grade levels on their experiences teaching nuclear science and their thoughts about ANS’s instructional materials. The webinar will conclude with a Q&A session with the panelists.
Registration is required for this Nuclear Science Week event.
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 | dx.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.