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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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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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.
Y. Sun et al.
Fusion Science and Technology | Volume 60 | Number 3 | October 2011 | Pages 899-904
Tritium Storage | Proceedings of the Ninth International Conference on Tritium Science and Technology | doi.org/10.13182/FST11-A12562
Articles are hosted by Taylor and Francis Online.
To efficiently confine the gaseous deuterium and tritium, which are the important fuels in the development of fusion energies, China has developed a series of hydrogen resistant stainless steels, named as the HR series of stainless steels. The mechanisms of the interactions between tritium with the decayed helium-3 and these stainless steels were investigated by theoretical calculations, experimental observations or tests through gaseous tritium loading into the stainless steels and years of storage. Results showed that the China made HR stainless steels had good performance to resist hydrogen damage or hydrogen embrittlement. They are the ideal structure materials for tritium systems used in a fusion reactor like ITER. Nevertheless, tritium permeation at high temperatures are still high. Tritium permeation barriers with the aluminides on the surface of the components were successfully developed, which could greatly reduce tritium permeation flux down to 2~3 orders of magnitudes.