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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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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Nuclear Science and Engineering
June 2025
Nuclear Technology
May 2025
Fusion Science and Technology
Latest News
The 2025 ANS election results are in!
Spring marks the passing of the torch for American Nuclear Society leadership. During this election cycle, ANS members voted for the newest vice president/president-elect, treasurer, and six board of director positions (four U.S., one non-U.S., one student). New professional division leadership was also decided on in this election, which opened February 25 and closed April 15. About 21 percent of eligible members of the Society voted—a similar turnout to last year.
Masahiro Tanaka, Takahiko Sugiyama
Fusion Science and Technology | Volume 67 | Number 3 | April 2015 | Pages 600-603
Proceedings of TRITIUM 2013 | doi.org/10.13182/FST14-T89
Articles are hosted by Taylor and Francis Online.
To fabricate a tritium monitoring system with electrochemical hydrogen pumping attached, a tritium monitor system was constructed and assembled with a commercial tritium monitor and an electrochemical hydrogen pump using a proton conducting oxide. The hydrogen pump with CaZr0.9In0.1O3−α as the proton conducting oxide was operated at 973 K under electrolysis conditions using tritiated water vapor (HTO). The tritium molecules (HT) were extracted and controlled by the applied current over a range of two orders of magnitude. The tritium molecules have an advantage with respect to the tritium memory effect in the monitor because the tritium contamination is reduced. Next, a system feasibility test was conducted under various water vapor partial pressure conditions. Thus, the measurement of the tritium concentration via this proposed system was successfully demonstrated.