ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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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. Yamazaki, T. Oishi
Fusion Science and Technology | Volume 60 | Number 3 | October 2011 | Pages 1109-1112
Concept and Facility | Proceedings of the Ninth International Conference on Tritium Science and Technology | doi.org/10.13182/FST11-A12609
Articles are hosted by Taylor and Francis Online.
The contribution of tritium fuel system construction and operation to the global COE and the life-cycle GHG emissions is analysed using PEC reactor system design code for both magnetic confinement fusion (MCF) and inertial confinement fusion (ICF) reactors. This contribution is less than a few percents in the present model, but the CO2 emissions from the ICF fuel system are rather higher than those from MCF, because of the DT pellet fabrication processes.
