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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.
G. Pierini, R. Baratti, A.M. Polcaro, P.F. Ricci, A. Viola
Fusion Science and Technology | Volume 8 | Number 2 | September 1985 | Pages 2121-2126
Blanket and Process Engineering | Proceedings of the Second National Topical Meeting on Tritium Technology in Fission, Fusion and Isotopic Applications (Dayton, Ohio, April 30 to May 2, 1985) | doi.org/10.13182/FST85-A24597
Articles are hosted by Taylor and Francis Online.
The extraction of tritium from the liquid alloy 17Li83Pb has been examined taking into consideration the equations related to the design of “droplet spray” and “bubble” extractors in order to verify which are the higher tritium recovery efficiencies which can be realized so as to minimize the permeation of tritium into the water of the cooling system. As far as the droplet spray unit is concerned, the tritium extraction efficiency has been correlated to tritium pressure in the extractor, to the droplet radius and to the residence time of the droplets in the extractor. For the tritium desorption from the alloy, flowing countercurrent to a helium stream in a bubble extractor, the axial dispersion in the liquid and gaseous phases and the effects of gas phase expansion caused by reduced hydrostatic head in the extractor are taken into account. From the results of this study, both the bubble and spray droplet extractors seem to be very appropriate units for tritium recovery from the alloy. Moreover, in order to reach high extraction efficiencies for reducing the tritium permeation to the water cooling system, the spray droplet extractor appears more suitable.
