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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.
Muyi Ni, Qunying Huang, Yong Song, Xiaoqiang Chen
Fusion Science and Technology | Volume 60 | Number 3 | October 2011 | Pages 1125-1128
Concept and Facility | Proceedings of the Ninth International Conference on Tritium Science and Technology | doi.org/10.13182/FST11-A12613
Articles are hosted by Taylor and Francis Online.
A tritium analysis model for the fusion-based hydrogen production reactor FDS-III blanket system was developed, including the High Temperature Liquid (HTL) blanket and major components of the auxiliary system (such as TES, CPS, and HX etc.). Based on the model, tritium safety assessment on HTL blanket system was done by using the Tritium Analysis Software (TAS), in which various factors affecting tritium permeation were considered,. The results showed that most of the tritium released into the environment would permeate through the heat exchanger as HTO. And a reasonable compromise among the various requirements could be found to keep the tritium released from HTL blanket system under safety guide line, based on the fabrication technology of the He/H2O heat exchanger, the capability of vent detritiation system, etc.