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Conference Spotlight
2025 ANS Winter Conference & Expo
November 8–12, 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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Fusion Science and Technology
Latest News
Nuclear News 40 Under 40: The wait is over
Following the enthusiastic response from the nuclear community in 2024 for the inaugural NN 40 Under 40, the Nuclear News team knew we had to take up the difficult task in 2025 of turning it into an annual event—though there was plenty of uncertainty as to how the community would receive a second iteration this year. That uncertainty was unfounded, clearly, as the tight-knit nuclear community embraced the chance to celebrate its up-and-coming generation of scientists, engineers, and policy makers who are working to grow the influence of this oft-misunderstood technology.
C. Fagan, M. Sharpe, W. T. Shmayda, W. U. Schröder
Fusion Science and Technology | Volume 71 | Number 3 | April 2017 | Pages 275-280
Technical Paper | doi.org/10.1080/15361055.2017.1293456
Articles are hosted by Taylor and Francis Online.
The concentration of tritium in the adsorbed water layer on stainless-steel type 316 is notably higher than that present in the metal lattice. The absorbed waters play a key role in the migration of tritium into the metal. In this work, stainless-steel (type 316) surfaces were subjected to various pretreatments designed to alter the surface in order to probe the relation between surface conditions and total tritium inventories. These pretreatments included electropolishing and soaking in nitric-acid baths. Stainless-steel samples were loaded with tritium by exposure to a deuterium–tritium gas mixture at 25°C for 24 h. Total tritium inventories were measured using temperature-programmed desorption. The thermal desorption data show a reduction of 65% in total tritium inventory by electropolishing stainless-steel surfaces as compared to unmodified samples. It is also shown that treating the surfaces with nitric acid resulted in an increase in the tritium content by ~200%.