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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 Technology
Fusion Science and Technology
May 2025
Latest News
ANS designates Armour Research Foundation Reactor as Nuclear Historic Landmark
The American Nuclear Society presented the Illinois Institute of Technology with a plaque last week to officially designate the Armour Research Foundation Reactor a Nuclear Historic Landmark, following the Society’s decision to confer the status onto the reactor in September 2024.
Xiaosong Zhou, Shuming Peng, Xinggui Long, Shunzhong Luo
Fusion Science and Technology | Volume 60 | Number 3 | October 2011 | Pages 905-909
Tritium Storage | Proceedings of the Ninth International Conference on Tritium Science and Technology | doi.org/10.13182/FST11-A12563
Articles are hosted by Taylor and Francis Online.
Helium release from titanium tritide films at room temperature have been studied. The evolution of lattice defects in long-aged titanium tritide films is also investigated by X-ray diffraction (XRD) over a period of about 1600 days (>4 years). And the thermal desorption (TD) has been used to investigate the 3He release from titanium tritide film with 3He/Ti atom ratio from 0.006 to 0.325. Results of XRD, TD and helium release were synthesized. A continuum-scale evolutionary model of helium for aging titanium tritide film is described which accounts for major features of the tritide experiment data. The combined stress-assisted-block loop punching growth for random bubble arrays and an average ligament stress criterion predicts an onset of inter-bubble fracture in good agreement with the He/Ti ratio observed for rapid He release.