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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.
K. Tsukatani et al.
Fusion Science and Technology | Volume 60 | Number 4 | November 2011 | Pages 1543-1547
Interaction with Materials | Proceedings of the Ninth International Conference on Tritium Science and Technology (Part 2) | doi.org/10.13182/FST11-A12727
Articles are hosted by Taylor and Francis Online.
In this research, thermal desorption characteristics of deuterium retained at trap sites of W created by irradiation of 300 keV hydrogen ions have been studied. With 10 hours of annealing, about 85% of deuterium was desorbed at temperatures of 300 °C and 350 °C, while deuterium desorption at 250 °C was about 60%. To estimate trapping energy of trap sites in this damaged W, TMAP simulation was performed. The result shows that the trapping energy of 1.29eV well accounted for the result of 250 °C annealing. In view that in the literature the vacancy trapping energy of hydrogen in tungsten was estimated to be close to 1.43 eV and the sensitivity analysis has given an uncertainty for the trapping energy of the order of 0.1 eV, it appears that the dominant trapping site type in the investigated damaged tungsten consists of vacancies.
