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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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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Latest News
Webinar: MC&A and safety in advanced reactors in focus
Towell
Russell
Prasad
The American Nuclear Society’s Nuclear Nonproliferation Policy Division recently hosted a webinar on updating material control and accounting (MC&A) and security regulations for the evolving field of advanced reactors.
Moderator Shikha Prasad (CEO, Srijan LLC) was joined by two presenters, John Russell and Lester Towell, who looked at how regulations that were historically developed for traditional light water reactors will apply to the next generation of nuclear technology and what changes need to be made.
Yasuhisa Oya, Misaki Sato, Kenta Yuyama, Masanori Hara, Yuji Hatano, Masao Matsuyama, Takumi Chikada
Fusion Science and Technology | Volume 68 | Number 2 | September 2015 | Pages 358-361
Technical Paper | Proceedings of TOFE-2014 | doi.org/10.13182/FST14-931
Articles are hosted by Taylor and Francis Online.
Dynamics of tritium recovery using CuO catalyst and water bubbler was studied as a function of gas flow rate and CuO temperature. The rate constant of tritiated water formation by CuO catalyst at the temperature above 500 K was determined to be k [s-1] = 5.4×105 exp (-0.65 eV / kBT). For the flow rate less than 50 sccm, it was found that the reaction rate will be controlled by the desorption rate of HTO on the surface of CuO. These results were applied for the design of tritium removal system at radiation-controlled area. It was concluded that the reactor tubing with 1.0 meter length at 600 K will be suitable to reduce the tritium concentration less than 1/1000 and the longer reactor tubing will be required if the operation temperature will be lower than 600 K.