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Conference Spotlight
2025 ANS Winter Conference & Expo
November 9–12, 2025
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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NN Asks: What did you learn from ANS’s Nuclear 101?
Mike Harkin
When ANS first announced its new Nuclear 101 certificate course, I was excited. This felt like a course tailor-made for me, a transplant into the commercial nuclear world. I enrolled for the inaugural session held in November 2024, knowing it was going to be hard (this is nuclear power, of course)—but I had been working on ramping up my knowledge base for the past year, through both my employer and at a local college.
The course was a fast-and-furious roller-coaster ride through all the key components of the nuclear power industry, in one highly challenging week. In fact, the challenges the students experienced caught even the instructors by surprise. Thankfully, the shared intellectual stretch we students all felt helped us band together to push through to the end.
We were all impressed with the quality of the instructors, who are some of the top experts in the field. We appreciated not only their knowledge base but their support whenever someone struggled to understand a concept.
Ph. Cetier, J. Charuau, Y. Belot, S. Fauvel, C.H. Wu
Fusion Science and Technology | Volume 28 | Number 3 | October 1995 | Pages 1148-1152
Tritium Properties and Interaction with Material | Proceedings of the Fifth Topical Meeting on Tritium Technology In Fission, Fusion, and Isotopic Applications Belgirate, Italy May 28-June 3, 1995 | doi.org/10.13182/FST95-A30562
Articles are hosted by Taylor and Francis Online.
This presentation describes experiments to investigate the sorption of tritium on carbon dust of different particle sizes and specific surface areas. The conditions of exposure were determined at the first wall of the tokamak. These conditions include low tritium pressures and depending on the operation phase, temperatures varying between 25°C and 1000°C. The simulation of these conditions inside an exposure chamber were necessary in order to design and construct a specific exposure device that could be adapted to these unusual conditions. Initial sorption data were obtained for carbon dust derived from a JET first-wall tile. The amount of tritium sorbed into or onto the carbon dust is between 0.1 and 10 mg T per kg C for a 24 hour-exposure duration. It increases with dust temperature. Other determinations, dealing particularly on the influence of exposure duration, are required to interpret this initial data.